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KINTIC-2 User's Manual

1. t 0 gt step for material motion onset of material motion end of micro interval or end of internal thermodynamics interval PL coolant flow 75 coolant plenum upper axial blanket absorber radial core zone core zone 2 blanket reflektor lower axial blanket follower fission gas Fig 4 Scheme of original reactor configuration 76 Fig 5 Subzone configuration for calculation of group constants original reactor configuration 77 channel 1 2 3 4 5 6 4 Fig 6 Thermodynamics representation original reactor configuration i axial zone which is not correlated with neutronics representation axial feedback zones y expansion zone 78 23 24 3128 39 35 47 42 53 53 2740 13531 43 38 radial feed back zones Fig 7 Feedback and feedback zones Numbers Zone number composition number Original reactor configuration 79 6 0 Q 9 0 0 4 Q o 9 q 9 Q Exi Q O parer 18 19 4 20 21 0 0 9 Q 0 9 22 0 60 e 0 Q w Q mG 23 4 10111213 4 15 16 1 Fig 8 Neutronics mesh zone configuration comprising feedback and non feedback zones outer edge o
2. NSPLT NSFCI TI I 1 NKKN I 1 NKKN IPL NNFCI KAPRML IFLAG1 IFLAG2 IFLAG3 GLOBREAL CN T2 TETTA EPS I I 1 10 FAXEXP OPER PKONO IPDEC I 1 1 3 TKINNO TPLEN FTRO MAPL COOL 49 FRACTION FMSLB MUST BE REACHED 1 PLASTIC CLADOING DEFORMATION SPLSLB AND FUEL MELT FRACTICN FMSLB MUST BRE REACHEEL MINIMUM NUMBER OF AXIALLY COHERENT NOLES FOR WHICH SLUMPING CRITERION MUST BE FULFILLED DS NUMBER FOR PLOT OF SLUMPING PATTERN NE 23 249 25 0 PLOT FCI CRITERION FOR CHANNEL I 0 CLADDING TEMPERATURE AND FUEL MELT FRACTION MUST REACHED 1 PLASTIC CLADDING DEFORMATION SPLFCI AND FUEL MELT FRACTION MUST BE REACHEC MINIMUM NUMBER AXIALLY CCHERENT NCLES FOR WHICH FCI CRITERION MUST BE FULFILLED DS NUMBER FOR PLOT CF FCI PATTERN NE 23 24 25 0 NO PLOT 0 FLIQ IS USED 0 VBRKU IS USED SEE DATA ON POSITION 539 540 IN CHANNEL INPUT DS NUMBER OF UNIT FOR MAPLIB MESSAGES 23 24 25 9 2 TIME DERIVATIVE OF COOLANT DENSITY 0 FOR CNE PHASE COOLANT 1 TIME DERIVATIVE OF CCOLANT DENSITY EEING TAKEN INTO ACCOUNT 0 ADIABATIC HEATING IN CHANNEL 1 HEAT TRANSFER TO BYPASS BEING TAKEN INTO ACCOUNT CALCULATION IN BOILING ROUTINE PARTIALLY WITH DOUBLE PRECIS ION D DTHERWI SE CONSTANT CONSTANT RELAXATION PARAMETER FOR TRANSIENT CALCULAT
3. s s r s s X T s INPUT FCR DIXY IS CCNTAINED IN THE THREE BLOCKS DX DXDIF AND DXBUCK OF THESE LDIM AND DXBUCK ARE TO BE PROVIDED ACCORDING TO THE DIXY INPUT DESCRIPTION WITH NO ADDITIONAL RESTRICTIONS ARISING FROM THE USE OF DIXY IN CONNECTION WITH KINTIC 2 FOR DXDIF THE FOLLOWING RULES CONCERNING THE GEOMETRY HAVE TO BE OBEYED SEE CHAPTER 4 le OVERLAY OF REGION INPUT IS NOT ALLOWED 2 THE FIRST NKKOXNMD SEE BLOCK KINPUT ZONES ARE TO BE THE FEEDBACK ZONES INCLUDING THE ZONES ABOVE THE AXIAL BLANKET ALLOWING FOR AXIAL EXPANSION AFTER THESE NON FEECBACK ZONES MAY BE DEFINED IN ARBITRARY ORDER 3 AMONG THE FEEDBACK ZONES THE FIRST ZONES ARE THOSE PERTAINING TO THE FIRST RADIAL SEGMENT THE NEXT NMD ZONES THOSE F R THE SECOND SEGMENT ETC THE ZONES PERTAINING TO ONE SEGMENT MUST ORDERED ACCORDING TO THE DIRECTION OF THE COOLANT FLOW I Eo WITH CCCLANT ENTERING THE FIRST ZONE AND PROCEEDING THROUGH THE FOLLOWING ZONES ACCORDING TO THEIR ORDER DISTRIBUTION OF AXIAL ZONE HEIGHTS IN ALL RADIAL SEGMENTS MUST BE THE SAME FOR A NUMBER JF VARIABLES IN DXDIF IMPCRTANT RESTRICTIONS EXIST THEY WILL BE LISTED BELOW USING THE NOTATION FROM THE DIXY INPUT DESCRIPTION 170 NZ FROM BLOCK KINPUT IGED NE 1 OR 3 FOR NFEED NE O SEE BLOCK KINPUT ICHI GT 1l NGP NG FROM BLOCK KINPUT IQUE 0 NF71 JOINT 0 RECOMMENDED OTHERWISE
4. IBLE WITH THE KAPROS TYPE OF JNFORMATTED INPUT THE INPUT CARDS OF A CAPRI 2 STAND ALONE INPUT MAY BE DIRECTLY INSERTEL INTO BLOCK THEIN ONLY THE CONTROL CARDS CONTAINING THE CONSTANT CHAN AND THE CHANNEL NUMBER OR THE WORD END MUST BE ADDED THE FOLLOWING CONDITIONS MUST BE FULFILLED FCR THE FORMATTEE INPUT TO PE INSERTED DIFFERENT NUMBERS MUST BE SEPERATED BY AT LEAST CNE BLANK BLANKS MAY TURN UP IN THE STRING OF CHARACTERS DEFINING ONE NUMBER SIGNIFICANT ZEROS WAY NOT BE REPLACED BY BLANKS AND CCLUMNS 71 80 MAY NOT BE USED THE CHANNEL INPUT IS GOVERNED BY THE SAME RULES THAT AFFLY FOR THE CHANNEL INPUT OF THE STAND ALONE VERSION THE DATA OF THE FIRST CHANNEL NOT NECESSARILY CHANNEL NUMBER 1 NEED EE DEFINED ONLY IF THEY ARE NONZERO THOSE DF THE FOLLOWING CHANNELS ONLY INSOFAR AS THEY ARE DIFFERFNT FROM THOSE THE PRECEDING CHANNEL KAPROS CONTROL CARD K SIOX DBN THEIN TYP CARD PMzZKINPUT CONCATENATION SHOULD BE USED SEF BLOCK KINPUT CONTENTS DF BLOCK Kl K2 K3 K4 GUOBINT NCCE NKKN NM2 NM NMOB NMUB NMPL NN GECM LART 1 T 1 yNKKN ICNTL 9 CLC MP TPC IPOBDI IVOIO IEXP KPRUG IIREF TIAX NPAX TABB JERFOR NSSLB 1 I 1 48 CONSTANT CONSTANT NUMBER JF COOLANT CHANNELS LE 30 NUMBER DF AXIAL NODES INCLUDING PLENUM AND MIXING CHAMBER 1 30 NU
5. 3 The time dependent flux is seperated into a strongly time dependent amplitude A and a weakly time dependent shape function 4 with the additional constraint a 1 ac oka 0 gt 0 5 lt gt signifying multiplication and integration over all space and energy By inserting 4 into 1 and 2 multiplying 1 by 3 by y 2 by vt integrating and suitably subtracting the results the usual point kinetics equations are derived i 6 a B I er The coefficients are given by s _ 1 d r Xi I lt y 1 gt a yt d y gt 7 Loop e xk MM Beg i i 1 p 1 T t t sy gt Wa RAS yp Ma d i d d Mi isi M AM XP mM x zd i Up to this point the three different methods provided by KINTIC are equal The difference arises from the as sumptions made concerning the shape function For point kinetics j is assumed to be the steady state neutron dis tribution Point kinetics Vg 8 In the adiabatic method all time derivatives in 1 and 2 are neglected resulting an equation for y which differs from the steady state equation only in that the group constants contained in the operators S and M are time dependent An eigenvalue has to be introduced to guarantee a nonzero solution Adiabatic method O Sy 1 X MP y 9 i For the quasistatic method 4 is inserted in 1 and by
6. 3o In the core and blanket region axial and radial boundaries from the subzone configuration are to be included as boundaries of thermodynamics zones The axial mesh outside the core and blanket region need not be correlated The same axial mesh is to be used for all channels A radial segment may contain more than one thermo dynamics channel e g two with different burnup It is not possible to define thermodynamics channels pertaining to more than one radial segment 4 4 Geometry for feedback This geometry is shown in fig 7 Only the core and blanket zones are correlated with the thermodynamics zones including a small axial zone above the upper blanket into which the fuel elements expand Radially channels 1 and 2 and axially three zones in the middle of the core region are collapsed This picture illus trates the rules for forming the feedback mesh which are as follows Only the core and blanket zones are correlated with the thermodynamics mesh If axial expansion is to be treated an additional axial zone is to be added above the uppermost thermodynamics blanket zone for each channel The height of this zone is arbi trary but should be of the order of magnitude of the expected maximum expansion If axial expansion is suppressed no expansion zone needs to be defined uds b Radial and axial boundaries of the feedback mesh must coincide with boundaries of the thermodynamics mesh and must include
7. 2023500 1 HUELL 6 3025209 525 aV 519 aSTRUKa3 6 aCR5202 0475 aV 510 4 3 20 16023 1 aHUELLA 6 3285299 525 aV 519 e475 510 1 asTRUKa 9 1009 1 2 09603 1 1 aSTRUKa 2CR5202 l ANI 5903 1 1 4 5 NUFIN 3023808 1 525 g FE5603 525 2 096008 3 525 KUEHL 1 2309 1 2475 FE560a 3 0475 65 3PU3903 1 04002 1 9923508 1 2023808 1 525 5602 525 2 096099 a 525 aKUEHLa 1 9 2309 1 asTRUKa 6 3225209 475 FE5603 475 9 096029 3 475 3NA23023 1 38 1103 1 3C 1202 1 2 893002 1 9 159009 1 aFE5609 1 3 096024 1 KSIOX DBN NUDABL IND 3 TYP CARD PMN NUTE ST 214 00397 4100 0 0 0 ENDE 04100 5 300 600 100 til COND 1 26 NUFIN GO SM KI NWQ 900 1500 2100 aPU4108 1 a PU420a 525 aNB9I30a 525 6415 3M09608 2475 2 893082 475 525 NB9302 525 475 9302 475 aCR5202 1 2303 1 aFE5602 a NB 9302 1 aNI5 993 2 15 903 2 159089 aNI5904 66 CASE wee JDBCARN s REGIONZ290K4 1 30 FORMAT PR DDNAME FTA2FOOL EXEC KSS Ks FT22F291 DD DSN A1 IIINNN UNI T 3330 VOL SER TSTLIB DISP NEW KEEP S PACE ITRK 2 K FT23F001 DD UNIT SYSDA SPACE I TRK 3 25 921 DD DOSN T1630Z IIINNN UNIT 3330 VDL SER TSTLIB DISP SHR K FT26F001 DD DUMMY YIKSSY
8. PERTURBING COMPOSITION 1 G T SEE K20 CONTINUE WITH K20 1072 1 1 1 2 1 1 1 3 2 COMPOSITION NUMBER OF PERTURBED ZONE FOR NFEED LT O DO NOT SPECIFY FEEDBACK ZONES NAME OF FIRST MACRO MATERIAL 5 ALPHANUMERTCAL CHARACTERS ITS VOLUME FRACTION IS MULTIPLIED BY G T NAME OF SECOND MACROMATERIAL WHICH FILLS UP PRIVIDES THE SPACE OF THE FIRST GNE VACUUM MAY BE SPECIFIED IN CASE THE SPACE IS NOT TO BE FILLED UP PROVIDED OTHERWISE 5 ALPHANUMERICAL CHARACTERS 518 K19 K20 521 K22 523 K24 525 K26 K27 39 CUNTINUE WITH K20 IDZ30 T COMPOSITION NUMBER FIRST PERTURBED ZENE FOR NFEED LT O 00 NOT SPECIFY FEEDBACK ZONES MANA3 I MACRO MATERIAL ITS VOLUME FRACTION IN THE FIRST PEATURBED ZONE IS MULTIPLIED BY G T THE DIFFERENCE FROM INITIAL STATE COMING FROM GOING TO THE SECOND PERTURBED ZONE IDZ40lI COMPOSITION NUMBER OF SECOND PERTURBEL ZONE FOR I 1 NZP NFEED LT O DO SPECIFY FEEDBACK ZCNES NSTT NUMBER OF POINTS DESCRIBING THE WEIGHTING FUNC TION GUT NORMALLY NSTT GEs2 BUT FCR TIME IN DEPENDENT MIXING OF E Ge CONTROL ROC OR FOLLOWER ZONES WITH FEEDBACK ZONES NTYPz1 NSTT21 THEN AND T2 TMX IN KL TIME SEC GILT WEIGHTING FUNCTION AT TIME TI I I 1 NSTT CONTINUE WITH S10 DCN CONSTANT NDCN NUMBER OF SUBZONES AND VARIANTS OF SUBZONES IN THE REACTOR FOR EACH VARIANT
9. 10 10 0 000 0 015 0 030 0 045 0 060 0 075 Ele SES FIG 21 CASE CD POWERCT AXIAL INTEGRAL SF POWER KW E 10 E CHANNEL 1 O CHANNEL 2 93 0 000 0 015 0 030 0 045 0 060 FIG 22 CASE CD AX INTEGRAL Sr POWER 0 075 94 CHANNEL 1 CHANNEL 2 A MAXIMUM W iO 10 vr T marec 0 000 9 015 0 03 0 045 0 060 0 075 D FIG 23 CASE CD MAXIMUM POWER IN PIN 95 C CHAN o CHAN amp A CHAN 2 CHAN me CHAN CHAN MAX CENTER CENTER MAX AVERAGE AVERAGE MAX SURFACE SURFACE N N Roe gt gt r ns r 7 3 237 gt r cJ 225 000 a Y Zc Mi n x 150 000 75 000 IE MUR Eo lie 90 000 Wr ER RUE MORENO ENCEINTE 0 000 0 015 0 030 0 045 0 060 0 075 554 FIG 24 CASE CD FUEL TEMPERATURES 96 CHANNEL 1 CHANNEL 2 I CT 0007053 1 I 000 078 0007015 000 706 00070 CS a 4 000 08 0 030 Tall 0 015 Q Q D FIG 25 CASE CD CLAD TEMP HOTTEST NODE DU P CLE Gg 150 540 000 590 000 640 000 690 000 490 000 440 000 97 F rl 2 HOTTEST NODE CHAN
10. 2 HOTTEST NODE A CHAN 1 MAXIMUM CHAN 2 MRXIMUM 0 000 0 015 0 030 0 045 225454 FIG 26 CASE CD COOLANT TEMPERATURE 98 2 m CHANNEL 1 CHANNEL 2 ers 8 SEREA 92 62 CES Ce Zaa L DSJ 22 CE To CS 5 LI cg 5 T T T 1 1 0 000 0 015 0 030 0 045 0 060 0 075 PERE FIG 27 CASE CD REL CHANGE OF MASS FLOW 99 Acknowledgements The author whishes to thank her co workers Bachmann R Fr hlich M Gr ner S Kleinheins W Maschek and G Willerding for their help in organizing and pro gramming the code and in preparing and typing the manuscript
11. CLADDING DENSITY G CM 3 COOLANT DENSITY G CM 3 STRUCTURE MATERIAL DENSITY G CM 3 SPECIFIC HEAT OF FUEL CAL G DEG C SPECIFIC HEAT CLADDING CAL G DEG C SPECIFIC HEAT OF COOLANT CAL G DEG C SPECIFIC HEAT OF STRUCTURE MATERIAL CAL G DEG C HEAT TRANSFER COEFFICIENT FUEL CLADDINCG CAL CM w 2 SEC DEG CI HEAT TRANS FER COEFFICIENT CLADDING COOLANT CAL CM 2 SEC DEG C HEAT CONDUCTIVITY OF FUEL CAL CM G CEG C HEAT CONDUCTIVITY OF CLADDING CAL CM G DEG C K6 K7 58 59 K10 45 KKN NUMBER OF CHANNEL MI NUMBER OF DIFFERENT SETS OF FOLLOWING DATA ALPHA BETAAB s FF VOLUME FRACTION OF COOLANT VOLUME FRACTION OF SPACER BETAKA T VOLUME FRACTION OF SUBASSEMBLY WALLS BETATO I VOLUME FRACTION OF OTHER MATERIALS COMPR IS ING COOLANT SPACER AND SUBASSEMELY WALLS ECT CLEARANCE BETWEEN FUEL AND CLADDING CM Iz1 MI MZ T NUMBER OF FOREGOING DATASET PERTAINING TO AXIAL I 21 NM NODE I KKN NUMBER OF CHANNEL AUSBAX LINEAR AXIAL EXPANSION COEFFICIENT FOR FUEL 1 DEG C AUSTAX LINEAR AXIAL EXPANSION COEFFICIENT FOR CLADDING 1 C AUSSAX LINEAR AXIAL EXPANSION COEFFICIENT FOR STRUCTURE MATERIAL 1 DEG AUSBON VOLUME EXPANSION COEFFICIENT FOR BONDING 1 DEG AUSBRA LINEAR RADIAL EXPANSION COEFFICIENT FCR FUEL 1 DEG C AUSCRA LINEAR RADIAL EXPANSION COEFFICIENT FCR CLADDING
12. EPS3 in block KINPUT This number decides whether the macro interval is to be recalculated c3 Maximum number of shape function recalculations for one macro interval NIT in block KINPUT Normally NIT O in which case the macro interval is recalculated if necessary but the new shape function is calculated only once 3 Organization of the code system KINTIC 2 It is not the purpose of this description to give a do cumentation of the internal structure of KINTIC 2 and related programs Rather only that part of such infor mation will be presented which is necessary for the user to understand the working of the code and the options provided 3 1 Modules and data organization Since KINTIC 2 is controlled by the KAPROS system program and data organization are tailored according to the options provided by KAPROS Thus the system KINTIC consists of a number of modules which communicate via data blocks The Oa controlling module is called KINTIC which mainly organizes the data and controls the flow of calculations At the moment the following modules are part of the system Input testing KINPRM test of input for neutronics new and old thermohydraulics Core of KINTIC 2 system KINTIC controlling module data organization and minor calculational tasks AIREKI solution of point kinetics equations EVA two dimensional evaluation module for calculating integral parameters space dependent precursor concentrations po
13. INSTIT OR THEIN IS PRESENT CONCATENATION OF INPUT BLOCKS I E PM KETT FOR ALL BLOCKS EXCEPT THE LAST ONE SHOULD BE USED TO GUARANTEE A FULL INPUT TEST CONTENTS OF BLOCK 51 FOR START OF CALCULATION K8 FOR RESTART K2 F R CUTPUT OF INPUT DESCRIPTION K39 K2 CHCKI CONSTANT NCHCI NCHEC FROM FOREGOING RUN E 1 2 OR 4 NBCHI DS NUMBER OF RESTART FILE 23 24 53 IF NCHCI LT 23 CONTINUE WITH S31 OTHERWISE K4 K 1 CONTROL NUMBER FOR CONTINUATION OF EVALUATION FILE KTPOUT SEE K8 9 NO EVALUATION OUTPUT 1 CONTINUE SAME FILE 2 CONTINUE ON NEW FILE START ON NEW FILE 55 FOR NFEED GE O CONTINUE WITH S31 OTHERWISE K6 TNEVALT s CONTROL NUMBER FOR CONTINUATION OF EVALUATION 2 5 FILES ICLCMP NFCIPL IVOID AND NSPLT THIS 9RDER SEE K4 IN BLOCK THEIN DEFINITION AS IN K4 ST CONTINUE WITH 531 KS START CONSTANT NG NJMBER OF ENERGY GROUPS LE 26 NV NUMBER OF PRECURSOR GROUPS LE 6 NZ NUMBER OF FEEDBACK AND NON FEEDBACK ZCNES 1 200 NUMBER NEUTRONICS MESH POINTS NKKD NUMBER OF RADIAL SEGMENTS FOR FEEDBACK NMD NUMBER DF AXIAL SEGMENTS PER RADIAL SECMENT FOR FEEDBACK ANMAX MAXIMUM NUMBER OF RADIAL ZONES IN PELLET USED FIR THERMODYNAMICS REPRESENTATION NFEED 1 OLD THERMODYNAMICS MODULES 9 NO THERMODYNAMICS AND FEEDBACK 1 CAPRI 2 THERMODYNAMICS MODULES NAUS 12 MAXIMUM QUTPUT FOR TESTING 2 BIG OUTPUT K9 S10 K
14. SEC FUEL CENTRAL TEMPERATURE IN HOTTEST NODE FOR EACH CHANNEL DEGe C FUEL AVERAGE TEMPERATURE IN HOTTEST NODE FOR EACH CHANNEL DEG C FUEL SURFACE TEMPERATURE IN HOTTEST NODE FOR EACH CHANNEL DEG C CLADDING CENTER TEMPERATURE IN HCTTEST NODE FOR EACH CHANNEL DEG C COOLANT TEMPERATURE IN HOTTEST NODE FOR EACH CHANNEL DEG C COOLANT TEMPERATURE AT UPPER CORE BOUNDARY FCR EACH CHANNEL DEG C FRACTION OF LIQUIC FUEL IN HOTTEST NODE FOR EACH CHANNEL DEG C RELATIVE CHANGE OF MASS FLOW RATE FOR EACH CHANNEL FUEL COOLANT INTERACTION FILE NFCIPL Wm SAT RECCRD LENGTH 181 1 2 31 32 61 62 91 92 121 122 151 152 181 D TIME SEC COOLANT TEMPERATURE IN REACTION ZONE DEG C FUEL TEMPERATURE IN REACTION ZONE DEG C PRESSURE IN REACTION ZONE LOWER LIMIT OF REACTICN ZONE UPPER LIMIT OF REACTION ZONE SODIUM VOID FRACTION IN REACTION ZONE SODIUM BOILING FILE IVOID RECORD LENGTH 1 LO NKKN 1 E TIME SEC FOR EACH CHANNEL 10 POSITIONS CONTAINING THE UPPER AND LOWER BOUNDARIES OF 5 BUBBLES IF LESS THAN 5 BUBBLES ARE PRESENT DEFAULT VALUES 1 6 ARE INSERTED SLUMPING FILE NSPLT fee ES SD 58 RECCRD LENGTH 61 1 TIME SEC 2 31 LOWER BOUNDARY OF SLUMPING MATERIAL 32 61 POSITION OF LOWER BOUNDARY OF FALLING UPPER AXTAL BLANKET THE CONTENTS OF THESE FILES MAY BE USED FOR PRODU
15. Similar to the initiation of fuel coolant interaction slumping is initiated when the fraction of molten fuel and either the mean cladding temperature or the plastic deformation of the cladding exceed user specified limits in a specified number of axial nodes At present a simple three zone model is employed for the description of material movement 8 The middle fuel segment for which the slumping criteria are fulfilled moves into the free space between the lower pins and at the same time the upper pin segments loose their support and fall down Movement of the slumping segment is described as viscous flow whereas the fall of the upper segments is governed by gravitation friction and the pressure gradient Fuel and cladding material are assumed to move coherently In the future it is planned to integrate a seperate module describing cladding motion and solidi fication It is possible with the modules described in this section to calculate the thermodynamics and material motion in the predisassembly phase of a core disruptive accident in a conservative manner Other modules might be added It must be stressed that in particular the configuration occuring in the so called transition phase cannot be modeled since KINTIC 2 assumes that all fuel subassemblies are intact In addition an automatic switch over to dis assembly is not realized at the moment Possibly the future development on the KINTIC 2 system will include an
16. up to 30 If during a calculation in the KAPROS system control is transfered from one module to another this entails shuffling the old module out of the fast memory and re loading the new module In the KINTIC 2 system trans fer of control takes place extremely often typically 200 400 times per macro interval Shuffling the modules in and out of the fast memory at every change of control causes a lot of data transfer overhead Therefore KINTIC 2 offers the option to keep the modules which are used most often in the fast memory during the whole calculation This is achieved by putting KAPRST 1 in the block KINPUT internally use is made of the KAPROS utilities KSLORD and KSLADY If KAPRST 1 KINTIC 2 needs a bigger memory than if KAPRSTzO in which case modules are shuffled and out of the fast memory in the normal way Thus KAPRST 1 should be used for production runs whereas KAPRSTzO for small test runs Approximate additional 24 fast memory requirements for KAPRST 1 as compared to KAPRST O 100 K for the old thermodynamics or no feed back 550 K for the new thermodynamics Dynamic dimensioning is used in all of the KINTIC 2 system except the CAPRI 2 thermodynamics modules There fore no upper limits or fairly high ones group number lt 26 are given for a number of variables The dimensions of a case to be calculated are always limited by the fast memory available which is tested for sufficiency at the start
17. 0 504851 02 2 0 24795 01 3 0 771097E 02 4 0 410375 02 5 0 133110 01 6 0 222437 03 7 0 958653 02 8 0 127620E 03 9 0 333236E 02 446 WQF IN 00352 90 21 SIGMA SABBR 5 ABBR 757352 26 1 0 2 1 1 0 4 5 COKNT 1 26 1 ENDE INUFIN 64 6 KSIOX DBN NJDABL IND 8 TYP CARD PMN NUTEST 1 4 0C397 446 0 0 0 00446 352 0 0 3 446 SIGMA SABBR KOMPQO 446 0 0 0 446 KCMPD 2 GReKFKINROOLA 2 26 1 0 18 445 8 1008 110C 120 520 560 0960 230 8930 1 5900 1L60PU3 90PU400PU410a PU420SPP90U2350U2380V 5108 446 6 4 0 260524E 02 5 0 845038 02 6 0 141213 03 7 0 189532 01 8 0 810186 04 9 0 211552 02 446 WOFIN 00352 90 21 SIGMA SABBR S ABBR ST352 2610 2110 5 5 CDKNT 1 261 ENDE INUFIN KSIOX DBN NUDABL IND 1 TYP CARD PMN NUTEST 0 00397 2291090 ENDE 102291 2250 20 1 26 5 1 SABBR 1 02250 0150 16 1 PU390 0032 08 400 0032 08 PULO 0032 08 PU420 0032 08 U2350 0032 08 U2380 0032 08 4 QBRENNa 7 30 1609 1 3PU3903 1 3PU4003 1 410 1 3PU4202 1 2023502 1 9023809 1 DHUELL 3CR5203 525 aFE5608 525 09608 525 525 590 2525 5102 525 KUEHL 1 3NA2303 1 QSTRUK3 5 3CR5203 475 FE560 475 09608 475 NB9308 475 aNI590a 475 V 5109 475 4 7 30 1603 1
18. 1 DEG C AUSSRA LINEAR RADIAL EXPANSION COEFFICIENT FCR STRUCTURE MATERIAL 12 DEG C AUSKUE VOLUME EXPANSION COEFFICIENT FOR COOLANT 1 DEG FOR KONSI BLOCK KINPUT 67 0 CONTINUE WITH 59 KIO OTFERWISE END OF BLOCK FOR EACH CHANNEL K190 KKN NUMBER OF CHANNEL NTT NUMBER OF DIFFERENT SETS CF FOLLOWING TSO 0 1 FUEL TEMPERATURE USED FCR PREPARATION CF NUCL IDE DENSITIES IN CALCULATION OF GROUP CONSTANTS 0 1 SAME FOR CLADDING SAME FOR COOLANT TSOUT s SAME FOR STRUCTURE MATERTAL T 1 NTT MTU NUMBER OF FOREGOING DATASET PERTAINING TC AXIAL I 1 NM NODE I END BLOCK FOR EACH RADIAL FEEDBACK CHANNEL K13 THEN END OF BLOCK NK AN NUMBER OF THERMODYNAMICS CHANNELS PERTAINING TO THE FEEDBACK CHANNEL LE 10 THEIR NUMBER IN THE SEQUENCE THERMCCYNAMICS RIC 1 G T I 1 NKAN NMIUI I 1 NMD 46 CHANNELS IN BLOCK THEIN INNER RADIUS THERMODYNAMICS CHANNEL CM OUTER RADIUS OF THERMODYNAMICS CHANNEL CM WEIGHT OF THERMODYNAMICS CHANNEL IN FEEDBACK CHANNEL NEED NOT BE NORMALIZED AND TFUS MAY BE Ee Ger THE NUMBER FUEL SUBASSEMBL IES PERTAIN ING TO THE THERMODYNAMICS CHANNEL FOR EACH AXIAL FEEDBACK ZONE NUMBER CF AXIAL THERMODYNAMICS ZONES PERTAINING TO IT F R THE EXPANSION ZONE NMI O OTHERWISE NMI GT O 47 6 4 INPUT BLOCK THEIN THIS BLOCK IS TO BE PROVIDED ONLY FOR THE START OF A CALCULATIO
19. 267 268 269 270 271 272 273 27 275 276 277 FFGMOL I 1 NM FPCG FPEQ FPUR FP SWCS FPSWEQ FP SWUR FRELML FRELCS FRELEQ FRG FRHOSM FTAGE FVARRH FVSWF 52 MOLECULAR WEIGHT OF FISSION GAS AXIAL DISTRIBUTION OF NEUTRON FLUX WITH ENERGY GREATER THAN 1 MEV FOR CALCULATION OF SWELLING OF CLADDING 1 CMx 2 SECI POROSITY CF COLUMNAR GRAIN FUEL DIRECTLY AFTER CHANGE DF STRUCTURE POROSITY OF EQUIAXED FUEL DIRECTLY AFTER CHANGE OF STRUCTURE POROSITY OF UNRESTRUCTURED FUEL REDUCTION CF FUEL POROSITY DUE TO FUEL SWELLING FOR COLUMNAR GRAIN FUEL SAME AS ABOVE FOR EQUIAXED FUEL SAME AS ABOVE FOR UNRESTRUCTURED FUEL FISSION GAS RELEASE OF MOLTEN FUEL FISSION GAS RELEASE OF COLUMNAR GRAIN FUEL FISSION GAS RELEASE OF EQUIAXED FUEL UNIVERSAL GAS CCNSTANT 1 E 3 W SEC MOL DEG C SMEAR DENSITY OF FUEL IRRADIATION TIME D PARAMETER FOR TRANSIENT FUEL SWELLING STATIONARY FACTOR FOR FUEL SWELLING KG M 3 C CPERATING DATA POS IT ICN CONTENTS 301 302 303 304 333 334 363 364 393 394 423 De TKOUT FFZ0 FSPRIN ANTBUID I21 NM2 ANTC I I 1 NM2 ANTK I I 1 NM2 5 1 I 1 NM2 POSITICN CONTENTS 424 425 BOND BONDP 426 455 DPOLI 456 485 I 1 NM2 DPPL I I 1 NM2 t EXPL AN AT ION STATIONARY COOLANT TEMPERATURE AT CUTLET DEG AXIAL FO
20. 294 1974 10 11 12 13 71 Ott D A Meneley Accuracy of the Quasistatic Treatment of Spatial Reactor Kinetics Nucl Sci Eng 36 402 1969 D H Cho R O Ivens R W Wright Pressure Generation by Molten Fuel Coolant Interactions under LMFBR Accident Conditions CONF 710302 p 25 1971 W Zimmerer PLOTCP Ein Fortran IV Programm zur Erzeugung von Calcomp Plot Zeichnungen KFK 2081 1975 W H bel Abstract No ENEA 184 of the ENEA Computer Programme Library 72 Read input initial organization NOR DIXIN THINIT Calculate inter mediate group constants QSUM Calculate inter mediate steady state flux DXDIFF Calculate power distribution EVA Feedback or criticality search Calculate inter mediate steady state thermo dynamics STATEM or STATO BREDA Make necessary changes to geom etry KEFFIT z Geometry group constants thermodynamics suffi demu iterated 7 KEFFIT no yes lt Iteration of steady state a conditions Calculate final steady state group constants 9 SUM Calculate final steady state flux and adjoint DXDIFF Calculate power distribution steady state precursors estimate ramp rate divide by k EVA Calculate final steady state thermo dynamics STATEM or STATO BREDA BLOTH Transient part Final determination of steady state conditions Fi
21. 39260815 3 49 15 3 31 15 2074415 1 94 15 80 15 2 15 264 14 05 085 135 05 202 1 29 6 8314 3 9100 441 3 015 301 3 564 50 2 304 21 21 969 334 21 21 35357 364 21 21 0953246 394 21 21 041292 424 2 8 4 1 7 432 12 12 865 462 12 12 95 495 8 8 247 516 1 3 3 6 5219 01 Oo Le 1 1 9 80665 6 1400 530 11 0 600 5 0117 10 3 307 091954 001 221 9 3 O CHAN 2 TEND KSIOX DBN DX LDIM TYP CARD PMN KETT LDIM 16 8 12 5 DBN DXDIF TYP CARD PMN PRDIXY DIXY 00 KN 14 2 21 30 01 0 0 0 20 1 0 01 ICh 6 2 0005 3 7104 1 110 REGN 0 41313 16 113 11 13 213711 31357 5 1 3 3 5 10 1 31 3 9 3 5 19 11 3 5 9 1 858513 6 5 8 13 16 75835 1258 13 HSTP 70 2 24 2 32 3 T8 VSTP O 13 182 2 176 6631 2 136 4831 1 124 1833 7 40 1833 1 25 DXNF 0 GO SM KINTIC ML 3 29 69 CASE D JOBCARD REGION 440K T IME 3 FORMAT PR DDNAME F T42F 001 EXEC KSG K FT44F001 DD IK FTOLFOOL DD IK FT2OFOIL DD K FT21F001 DD IK FT22FIIL DD K FT23F001 DD K FT26F201 DD IK FT2TFODL DD K SYSIN DD SPACE 3064 210 D UMM Y DS A2 1 3330 01 5 18 015 010 DSN A3 IIINNN UNIT 3330 VOL SER TSTLIB DISP OLDO KEEP DSN A4 TIT INNN UNI T 3330 VOL SER TSTLIB DISP OLD KEEP UNIT SYSDA SPACE ITRK 10 DUMMY DSN CO TIINNN UNIT 3330 VOL SER TST
22. 446 SIGMA SABBR KOMPO 446 000 446 KOMPO a26 GR KFKINRODOLA 26 1 18 446 1908 110C 120CR 52 GFE 560 0960 230NB930NI 5900 160PU3 90PU4 OOP U410 a aPU420SPP90U2350U23380V 5103 446 l4 4 0 3344 70E 02 5 0O0 110890E Ol 0 156334 03 7 0 103501 01 8 0 104014E 03 9 9 247123 02 10 0 125310 01 11 0 151025E 02 12 0 443006E 03 13 0 503416 04 14 0 100683E 04 16 9 106296 04 17 90 428120 02 18 0 658087E 04 446 WOFIN 00352 00 21 SIGMA SABBR sST3525 26 1 0 2 1 1 O 25 CDKNT 1 26 1 NUFIN KSIOX DBNZNJDABL4 INDz6 TYPz CARD PNN NUTEST 2635 14 700397 446 000 2004464 352 0 0 3 446 SIGMA SABBR KOMPO 446 0 0 0 446 KCMPO 926 68 1 0 26 1 0 18 446 8B 1008 1106 L20CR520FE560MO960NA230NB930NI5900 160PU3 90PU400PU4 10 9 04205 900235002380 5103 446 10 4 9 331770 02 5 0 110016 01 6 0 154850E 03 7 0 107574 01 28 0 103175E 03 9 0 244911E 02 10 9 138484E 01 16 0 173106 04 17 0 690691 02 18 0 658638E 04 446 WOFIN 700352 00 21 SIGMA SABBR SABBR 57352 2610 2110 35 CDKNT 1 26 1 SENDE SNUFIN KSIDX DBN NUDABL IND T TYP CARD PMN NUTEST 1 4 003971 446 0 0 O ENDE 00446 352 0 0 3 446 SIGMA SABBR KOMPO 446 000446 KOMPO 326 GR KFKINROOL3 9 26 1 0 18 446 1008 1102 1200852 0FE560M0960NA230NB930NI5900 160PU390PU400PU4108 QPU4205PP90U2350U2380V 5102 446 9 1
23. 5114 5 3387 6 8213 8 3569 9 26 92 84 530 4 1371 2750 3439 6196 7185 7475 6264 5068 3057 1659 502 5 844 9 383 3 99 16 22 64 206731 4678 03454 2002606 001385 1114 3 1268 4 3669 6 1441 7 26 10 25 57 23 160 2 356 7 506 1207 1689 2120 2026 1861 1242 733 7 238 1 539 1 353 3 148 3 56 3 15 43 2 988 3827 02617 009342 002868 5619 3 6429 4 2396 5 26 73 418 5 1121 2399 3097 5756 6503 1087 6216 5001 2941 1521 471 5 557 9 218 3 51 42 9 525 1 184 1226 008612 3944 3 5799 5 8717 58 9643 7 6774 8 7313 9 26 20 75 117 7 312 8 659 838 3 1647 1901 2117 1774 1503 925 8 509 9 158 2 350 2 174 1 52 59 14 56 2 155 496 06093 004598 001382 3555 3 6378 4 6863 5 24 54 6 0 ENDE 62 00446 352003 446 SIGMA SABBR KOMPO 446 000 446 KOMPO M26 GR KFKINRDOLA O 26 1 0 18 446 38 1008 LLOC 120CR52 0FE560M0960 230 930 15900 160PU390PU400PU4103 04205 90923500238 5103 446 0 3344 T0E 02 5 0 110890 01 6 0 156334E 03 7 90 193501 01 0 104014E 03 9 0 247123E 02 10 90 124809 01 11 9 104166 02 12 0 305554 03 13 0 347220E 04 14 0 694441E 05 16 0 121290E 04 17 0 483946 02 18 0 658087 04 446 WCFIN 700352 0606 21 SIGMA SABBR SABBR ST352 2610 2110 15 e CDKNT 1 26 1 3 NUF IN KSTOX 13 0 5 y TYP CARD PMN NUTEST 14 20639 7 46 000 ENDE 3 700446 35200 3
24. 86 200 000 MAXIMUM CENTER MAXIMUM AVERAGE 180 000 160 000 120 000 TEMPERATURE DEG C x10 100 000 I T 1 0 000 0 075 0 150 0 225 0 300 0 375 TAE FIG 15 CASE FUEL TEMPERATURES 87 LJ 930 SENS Na 31 rn I dte Enc Rr s 0007004 0007069 0007089 00070 9 0007099 0007059 0 375 S Lo Perla 1 Bt LOL gt Lo 8 WW IX 16 CASE B CLADDING TEMPERATURE N 88 670 000 5 MAX STRUCTURE COOLANT OUTLET A COULANT uo 668 000 669 000 667 000 666 000 TEMPERATURE 1 DEG 665 000 I T 1 0 000 0 075 0 150 0 225 0 300 0 375 FID 1 CASE B COOLANT STRUCT TEMP AMPLITUDE 89 0 000 FIG I T I 0 015 0 030 0 045 18 CASE CD BMPLITUDEL T 0 060 1 0 075 1 150 0 900 0 650 J 0 400 L 0 150 HIE 0 100 ot 90 TOTAL REACTIVITY 9 DOPPLER A FUEL CLADDING x COOLANT STRUCTURE MAT EXPANSIGN Or Pip EDS Cr c T T T T 2 000 0 015 0 030 0 045 0 060 0 075 DIE US FIG 19 CASE ED RERCTIVITY OT 9 000 9 000 9 000 91 0 000 0 015 0 030 0 045 0 060 0 075 TE S SEL FIG 20 CASE CD LIFETIMECT BETACT 92 10 POWER CMW 3 101
25. 9 As far as the original KINTIC 1 system is concerned the methods have been documented in 4 the concept for treating group constants and the modules to be used for creating a file of group constants for KINTIC 2 are published in 1 and need not be repeated here Thus after a first chapter treating the physical methods employed in the KINTIC 2 system in a more qualitative way two chapters follow which are meant to clarify the input The first one concerns the code organization only as far as a user has to be acquainted with it the second one treats the geometrical representation of the reactor Chapters on job control language input output and sample cases close the publication 2 Physics of the KINTIC 2 system This chapter gives a short summary of the physics underly ing the code KINTIC 2 and the approximations used For more detailed information the reader will be referred to the literature available on the different subjects 2 1 Nuclear Data The treatment of nuclear data has been basically altered for KINTIC 2 and a report containing detailed information on the new scheme for handling the group constants and on the creation of a file group constants for KINTIC 2 was published recently 1 Here only the details necessary for understanding the input for KINTIC 2 will be repeated For the treatment of group constants the reactor is subdi vided into so called subzones which are different with respect to init
26. SECTION IS FILLED 1 GRAVITY ACCELERATION M SECK 2 WAY BE IN CREASED OR DECREASED FOR SIMULAT IGN OF PRESSURE GRADIENT MELT FRACTION OF FUEL LEADING TO CNSET OF SLUMPING LIMIT OF TEMPERATURE IN CLADDING CENTER LEADING TO ONSET OF SLUMPING DEG C PLASTIC CLADOING LEACING TO ONSET OF SLUMPING EXPLANATION PLASTIC DEFORMATION OF CLADDING LEADING TO ONSET OF FCI LIMIT OF TEMPERATURE IN CLADDING CENTER LEADING TO ONSET OF FCI DEG C MELT FRACTION OF FUEL LEADING TO CNSET OF FCI RADIUS OF PARTICLES AFTER FUEL FRAGMENTATION CM 2 01 MIXING TIME CONSTANT SEC 5 3 FRICTION COEFFICIENT OF CHANNEL Jl O RE 25 HYDR DIAMETER ERROR LIMIT FOR INTEGRATION 5001 2 DISTANCE FROM UPPER CORE BOUNDARY TO FREE SURFACE CM FRACTION OF MOLTEN FUEL IN FCI ZONE PARTAKING IN FCI RATIO MASSES FUEL SODIUM IN FCI ZONE mn POSITION CONTENTS EXPLANATICN 601 630 631 660 661 690 691 692 5 1 2 1 I 1 NM2 1 I 1 NM2 TTBYPO 54 QUOTIENT OUTER SURFACE INNER SURFACE FOR STRUCTURE MATERIAL BYPASS TEMPERATURE FOR TIME TTBYPC DEG C BYPASS TEMPERATURE FOR TIME TTBYPI DEG C INITIAL TIME FOR CHANGE OF BYPASS TEM PERATURE FINAL TIME FOR CHANGE OF BYPASS TEMPERATURE 55 6 5 RESTRICTIONS CCNCERNING INPUT BLOCKS FOR DIXY
27. UNNECESSARY CALCULATION OF ADJOINT FLUX INRD 0 IDIT NE 1 FOR 0 NO FEEDBACK ZONE MUST BE DEFINED AND EXTENSION OR CONTRACTION CF ZONE NRRI MUST NOT AFFECT A FEEDBACK ZONE 56 7 OUTPUT OUTPUT OF KINTIC 2 CONSISTS OF A PRINTED GUTPUT CPTIONAL EVALUATION FILES THE PRINTED OUTPUT MAY BE GREATLY VARIED IN LENGTF USING THE DIFFERENT PRINTING OPTIONS THE OVERRIDING NUMBER IN THIS CONTEXT IS NAUS FROM BLOCK KINPUT IF THIS NUMBER IS 0 OR 1 OUTPUT FROM THERMODYNAMICS MODULES IS TO A LARGE EXTENT SUPPRESSED AND REPLACED BY SHORTENED OUTPUT OF THE MAIN THERMODYNAMICS DATA PRODUCED BY KINTIC 2 FOR PRODUCTION RUNS USE OF THIS OPTION IS RECOMMENDED UP TO FIVE EVALUATION FILES MAY PRODUCED BY A KINT IC 2 CALCULATION ONE IF CAPRI 2 THERMODYNAMICS MODULES ARE NOT USED THE FILES CONTAIN Le NEUTRONICS DATA AND IF THE OLD THERMODYNAMICS WCDULES ARE USED THERMODYNAMICS RESULTS 2 THERMODYNAMICS DATA FROM THE NEW THERMODYNAMICS MODULES EXCLUEING DATA FUEL COOLANT INTERACTION SODIUM BOILING AND SLUMPING 3 FUEL COOLANT INTERACTION DATA 4 SODIUM BOILING DATA 5 SLUMPING DATA ALL EVALUATION FILES ARE FILLED IN THE SAME WAY FIRST RECORD CONTAINS A 20 WORD IDENTIFICATION AND CNE INTEGER WHICH IS THE LENGTH OF ALL FOLLOWING RECORDS THEN ONE RECORD PER NORMAL TIME STEP FOLLOWS ONLY THE FINAL RESULTS OF INNER AND OUTER ITERATICNS ARE LISTED THE FIRST WORD GF E
28. is employed only if the amplitude has changed by more than a factor of 3 of the above criteria if fulfilled may define the of a normal step b1 b2 b3 18 KINTIC then proceeds with the thermodynamics cal culations for the normal interval just determined The processes occuring in the thermodynamics part of the program especially those described by the CAPRI 2 thermodynamics mostly require their own time scales These are internally determined and adjusted to the prescribed normal interval Since the calculational procedures of the CAPRI 2 thermodynamics could become too much strained by using unreasonably big normal intervals KINTIC 2 uses an estimate for a reasonable maximum length of the normal interval in case a calculation with the CAPRI 2 thermodynamics modules is done This maximum length is fed into the amplitude calcula tion via criterion a2 The following considerations determine the interval length The maximum change of radially averaged fuel tempera tures at any point in the reactor should be less than 35 K For the old thermodynamics modules a similar criterium stating that the maximum change of not overaged fuel temperature should not ex ceed 50 K is employed The onset of any type of material motion should be determined very accurately It is especially im portant that the onset of voiding is determined very well i e that the specified superheat is not much exceeded In some cases
29. normal steps between two shape function recalculations forms one macro interval see fig 3 Apart from the criterion just described the start or end of an external per turbation interval or the start of a material movement initiated in the thermodynamics modules always entails a shape function recalculation In KINTIC 2 as opposed to KINTIC 1 a linear shape function extrapolation employing the last two shape functions is automatically used whenever reasonable i e as long as no new material movement is initiated The user defined limits on the alterations of zone dependent contributions to the point kinetics coef 20 ficients are employed only if this extrapolation is not used i e for the first macro interval and for all intervals which start with the onset of some kind of material movement including movements defined via the external perturbation Otherwise the limits are doubled taking into account the much better shape function resulting from the extrapolation With the new shape function determined at the end of the macro interval point kinetics coefficients as given by 7 may differ from the ones calculated with the old extrapolated shape function As in the case of the normal step the user may specify how much of a difference he is willing to tolerate In case the difference exceeds this value the whole macro interval is recalculated This is the outer iteration employed by KINTIC as opposed to the in
30. of a calculation 3 2 MAPLIB messages In the CAPRI 2 thermodynamics modules extensive use is made of the MAPLIB library 3 containing material prop erties in the form of FORTRAN functions Even for a normal case these functions produce a number of messages and warnings which tend to inflate the printed output Therefore MAPLIB messages may be printed on a seperate dataset by putting KAPRML 6 in the input block THEIN If in the DD card of the dataset KAPRML a dummy is de fined the MAPLIB messages are suppressed 3 3 The restart option For even a medium case CPU times are too long for terminating a calculation in one run Therefore a restart option is provided No use is made of the KAPROS restart option since this would entail putting the restart blocks into the so called KAPROS restart life line in which the old blocks are automatically deleted 25 after seven days Since the number of restart blocks is big in the case of the KINTIC 2 system it can be fore seen that KINTIC alone would quickly fill up the restart lifeline or would not get enough space there The KINTIC system therefore uses a restart data set onto which all blocks necessary for the restart of a calcula tion are copied The restart routine does the reading or writing even for blocks which may not be defined in a special calculation in this case warnings are printed which normally may be ignored They are only helpful in case a restart fails Intern
31. small normal steps are required after the onset of material motion After the onset of voiding a maximum step length of 10 msec is speci fied for a superheat of more than 10 K and 5 msec for smaller superheat The first interval after the onset of fuel coolant interaction has a maximum length of 5 msec 19 The results of the thermodynamics calculation determine the reactivity at the end of the normal interval This is compared to the estimate used for the calculation of the time dependent amplitude and the same is done for the neutron lifetime and the effective fractions of delayed neutrons If the values disagree an iteration of the normal interval is warranted Here the user may specify how much of an error he is willing to tolerate at the end of a normal interval The normal interval may in addition be shortened and a recalculation enforced in case the convergence of the iteration turns out to be weak in spite of the nu merical acceleration procedures already built into KINTIC c After each normal step has been fully iterated the zone dependent contributions to reactivity neutron lifetime and effective delayed neutron fraction are checked for large local alterations since the last shape function calculation Bigger differences are taken as a sign that a shape function recalculation is necessary The user may influence the frequency of recalculations by defining the limits on the zone dependent alterations The sum of the
32. suitably rearranging the following equation results zc PAP Quasistatic method vor S y xM j 1 i tx i i 9 Time derivatives and precursors are explicitely accounted for by this method The two variants of the method differ in the way the left hand side of 1O is handled i 9 31 Normal quasistatic method 5 4c O 11 1 _ y t b t At Improved quasistatic method lt VUE 12 Since an external source is not included in 1 initially subcritical assemblies cannot be described in KINTIC Inclusion of this option would present no principal diffi culty but is not planned in the foreseeable future 2 4 Thermodynamics and material movements initiated by the transient A calculation with KINTIC may be run without any thermo dynamics and feedback mechanisms in which case the tran sient is governed solely by the external perturbation The normal case is of course a calculation including thermodynamics and feedback effects An older version of a thermodynamics module has been used in KINTIC 1 and was described in 4 This module has been kept in KINTIC 2 as an additional option but does not have much significance except for testing purposes It may treat steady state and transient heat conduction in fuel and cladding and heat transfer to the coolant and structure material A big number of effects is not included among them time dependent variation of c
33. the subzone boundaries The axial mesh must be the same for all feedback channels c Non feedback zones are uncorrelated with the thermo dynamics mesh Fig 7 already contains the zone and composition numbers from the neutronics input The composition numbers in parantheses in fig 7 may be arbitrarily chosen in fig 7 the first 6 compositions are core zone 1 compositions pertaining to subzone 1 the next 6 those of core zone 2 pertaining to subzone 2 etc The zone numbers which are given by the order of the cards defining the zones in the input for DIXY again obey certain rules a First all feedback zones are to be listed At the end of the zone input the non feedback zones follow in arbitrary oder b All zones pertaining to one feedback channel are to be listed consecutively in the direction of coolant flow The order of feedback channels is given by the order of zones in the DIXY input 4 5 Geometry for neutronics Part of this geometry has already been mentioned at the end of the last section The feedback and non feedback zones together form the zone mesh for the neutronics calculations This mesh is repeated in fig 8 and supple mented by dashed lines which together with the zone boundaries form the grid for the flux shape calculation Again certain rules are to be obeyed for the neutronics mesh 2326 a At least one point per zone must not be situated on a zone boundary b Thermodynamics radial channels
34. 0 181 210 211 212 213 214 215 216 217 219 Be EXPLANATION RBR I INNER RADIUS OF CLACDING IN EACH NODE M Iz214 NM2 DCAN IT THICKNESS CLADDING IN EACH NODE M I 1 NM2 RKUECI EQUIVALENT RADIUS OF COOLANT CHANNEL IN EACH Iz1 NM2 NODE M VDUFL I FOLLOWING QUOTIENT VCLUME OF STRUCTURE Iz1 NM2 MATERIAL PART OF ITS SURFACE IN CCNTACT WITH COOLANT IN EACH NODE M VSTRUK I VOLUME OF STRUCTURE MATERIAL PER M PIN IN I 1 NM2 EACH NODE M 3 M DBOND I SIZE GAP BETWEEN PELLET AND CLAECING IN I 1 NM2 EACH NODE M DELTZ I LENGTH OF AXIAL NODES M Iz 1 NM2 ALPHAS VOLUME FRACTION COOLANT PER CELL BETCAS VOLUME FRACTION OF CLADDING PER CELL BETSTS VOLUME FRACTION OF STRUCTURE MATERIAL PER CELL BETABS VOLUME FRACTION D SPACERS PER CELL BETKAS VOLUME FRACTION SUBASSEMBLY WALL PER CELL OMEGAS VOLUME FRACTION OF FUEL PER CELL ALFASP VOLUME FRACTION GAP BETWEEN SUBASSEMBLY WALLS PER CELL NGRID LT O DISTANCE BETWEEN GRIDS M PSI NGRID GT O QUOTIENT WICTF HEIGHT CF RIB NGRID LT O COEFFICIENT OF FLOW RESISTANCE DATA PIN DEFORMATION MODULE BREDA ind POSITION CONTENTS 220 23 231 232 EXPLANATION FACR I RADIAL POWER DISTRIBUTION IN PIN CEFAULT 1 1 1 VALUES 1 FABBM MAXIMUM ALLOWABLE BURNUP MWD TON FEP SML ERROR LIMIT FOR CALCULATION CF LIGUID FUEL VOLUME 233 234 263 264 265 266
35. 11 512 K13 S14 K17 KTPOUT KPLI KAPRST PERTUR NST TMX 38 7 1 MEDIUM OUTPUT INCLUDING SHAPE FUNCTION 0 SMALL OUTPUT WITHOUT SHAPE FUNCTION DS NUMBER OF NEUTRONICS EVALUATION FILE NE 234 24 25 0 NO SUCH FILE DS NUMBER OF INTERMEDIATE FILE NE 24 25 0 IF NO EVALUATION FILES ARE PRODUCER 29 TESTING OPTION SMALL REGION BIG OVERHEAD 1 PRODUCTION RUN OPTION BIG REGION LESS OVER HEAD CONSTANT NUMBER OF PERTURBATION INTERVALS GE 1 MAXIMUM TIME FOR PROBLEM SEC FOR EACH PERTURBATION INTERVAL 11 5 21 THEN K22 L NTYP T2 3 FOR PERTURBATION TYPE 5 2xNZP 2 NSTT FOR PERTURBATION TYPE 5 5 NZP 2X NSTT FOR PERTURBATION TYPE 5 4 NZP 2 NSTT FOR PERTURBATION TYPE PERTURBATICN TYPE O LE NTYP LE 3 START OF INTERVAL SEC END DF INTERVAL SEC 5 mM FOR PERTURBATION TYPE CONTINUE WITH 510 GTHERKISE 3 NZP NUMBER OF PERTURBATIONS 1 FOR NTYF 1 NUMBER OF PERTURBED FEEDBACK AND CR NON FEED BACK ZONES 2 NUMBER MACRO MATERIAL PAIRS UNE PAIR BE LONGING TO THE SAME ZONE 3 NUMBER OF MACRO MATERIALS IN PAIRS CF ZONES FOR PERTURGATION TYPE 1 CONTINUE WITH K15 FOR PERTURBATION TYPE 2 CONTINUE WITH K17 FOR PERTURBATION TYPE 3 CONTINUE WITH K19 1 71 1 52 1 T 1 NZP COMPOSITION NUMBER OF PERTURBED ZONE DO NOT SPECIFY FEEDBACK ZONES EXCEPT FOR NSTT 1 K20 SUBZONE NUMBER OF PERTURBING FRAC TION
36. 6th feedback zone is the one used for the des cription of axial expansion The transient is ini tiated by simulation of control rod movement 60 d A restart case to follow up case c Results of case c and d together were again plotted with PLTCP and are shown in fig s 18 25 61 CASE A e JOBCARD o sREGIONZA440K 1 30 FORMAT PR DDNAME FT42F001 SETUP DEVICE 2314 1D NUSYSO EXEC KSG DD DSN KNDF UNIT 2314 VOL SER NUSYSO DISP SHR 7 KeFTO4F 001 DD DSN GROUCO UNI T 3330 VOL SER KAPROS DI SPZSHR DD UNIT SYSDA SPACE 5 K FT25F001 DD DSN TIG30Z IIINNN UNIT 3330 VOL SER TSTLIB DISP INE A KEEP SPACE TRKy1 K SYSIN DD KSIOX DBNZKINWQI4 TYPZCARD PM zKETT 1115 SIOX DBNZKINCOI TYPZSCARD PMZPKINCO 3015 1 4 3BRENN3 0 8 94 326 aHUELL3 7 68 106 AKUEKLA 862 272 aSTRUKA 0 T T6 296 1 2 4 8 94 2326 aHUELLa 7 68 106 aKUEHL3 O 862 472 7 76 096 1 I 3 4 3BRENNO9 J 9 19 326 AHUELLa O 7 67 106 0 862 472 STRUK 7 76 096 1 4 1 STRUK 2 6 1 0 5 1 STRUK O 2 6 le 0 KSTOX DBN NUDABL IND 4 TYP CARD PMN NUTEST 1 4 00397 451000 ENDE 3 00451 46 0 10 SPEKT 26 12 47 79 98 186 2 383 9 488 2 927 5 1083 1159 970 4 797 483 6 264 5 81 12 150 6 70 15 17 73 3 641 3446 04184 002525 1671 3 6292 4
37. ACH RECORD CONTAINS THE TIME THE CONTENTS OF EACH RECORD THE CIFFERENT EVALUATION FILES IS LISTED BELOW A NEUTRONICS AND OLD THERMODYNAMICS FILE KTPOUT mne C C p n i dr V m vam m RECORD LENGTH 80 FOR NFEED LE O 140 FOR NFEED GT O 1 TIME SEC 2 AMPLITUDE 3 REACTIVITY 4 11 REACTIVITY EFFECT OF DOPPLER FUEL CLADDING COOL ANT STRUCTURE MATERIAL AUXILIARY MATERIAL BONDI EX PANSINN AND EXTERNAL REACTIVITY 12 NEUTRON LIFETIME SEC 13 SUM OF EFFECTIVE DELAYED NEUTRON FRACTIONS 14 19 DELAYED NEUTRON FRACTIONS OF INDIVIDUAL GROUPS 20 INTEGRAL POWER MW 21 5C POWER RELEASED IN GNE PIN FOR EACH CHANNEL KW 51 80 MAXIMUM POWER CM RELEASED IN PIN FOR EACH CHANNEL W CM END OF RECORD FOR NFEED LE O 81 90 MAXIMUM CENTRAL FUEL TEMPERATURE FOR EACH CHANNEL DEG C 91 100 MAXIMUM RADIALLY AVERAGED FUEL TEMPERATURE FCR EACH 191 110 111 120 121 130 131 140 57 CHANNEL DEG MAXIMUM TEMPERATURE IN CENTER OF CLADDING FOR EACH CHANNEL DEG C MAXIMUM STRUCTURE MATERIAL TEMPERATURE FOR EACH CHANNEL DEG C COOLANT TEMPERATURE AT OUTLET FOR EACH CHANNEL DEG MAXIMUM COOLANT TEMPERATURE FOR EACH CHANNEL CEG C THERMODYNAMICS FILE ICLCMP FOR NFEED LT O RECORD LENGTH 241 1 2 31 32 61 62 91 92 121 122 151 152 181 182 211 212 241 Ce TIME
38. ANT THE COEFFICIENTS ye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
39. CING LISTINGS OR PLOTS ESPECIALLY THE PLOT FACILITY PLOTCP 12 CAN BE APPLIED 59 8 Sample cases In the following lists are given of the job control cards and input for four jobs These are job for creation of a simple group constant file to be used in the following sample cases The pro grams described in 1 are used The data set created has 1 neutron and 1 precursor group 5 subzones core zone 1 core zone 2 blanket absorber follower and may accommodate up to 30 feedback and non feedback zones A sample case employing the old thermodynamics rou tines with 5 feedback and 3 non feedback zones with the non feedback zones containing fissionable material as well since they serve as a kind of driver The transient is induced in a rather ar tificial way by replacing coolant by fuel material in one of the driver zones In addition an external reactivity is fed in One coolant channel is used for thermodynamics The results of this case were plotted with PLOTCP 12 and are shown in fig s 9 17 A case employing the new thermodynamics modules with 6 feedback and 6 non feedback zones The non feedback zones comprise an absorber ringand a driver zone The feedback zones are collapsed axially and radially from the thermodynamics mesh which com prises two adjacent channels with 21 axial zones 12 of which are situated in the core blanket region These 12 zones are collapsed into 5 feedback zones the
40. ION OF FUEL TEMPERATURES 0 2 EXPLICIT 5 CRANK NICHOLSON le IMPLICIT LIMITS FOR ERRORS IN PIN DEFORMATION WCCULE DEFAULT VALUES PROVIDED IN PROGRAM IEXP 1 AXIAL EXPANSION IS MULTIPLIED BY FAXEXP FOR FEEDBACK TEXP 0 IRRELEVANT CONSTANT STATIONARY COOLANT PRESSURE AT INLET N Mx 2 STATIONARY COOLANT PRESSURE AT OUTLET N M x2 COEFFICIENTS DESCRIBING THE TIME DEPENDENCE OF PRESSURE DURING FLOW COAST DCWN DP P 0 EXP PDEC 1 T PODEC 2 T 2 PDEC 3 T 3 COOLANT TEMPERATURE AT INLET DEG C TEMPERATURE OF UPPER COOLANT PLENUM DEG C REFERENCE TEMPERATURE FOR COLD GEOMETRY DEG C CONSTANT NAME OF COOLANT IN MAPLIB Ge NAL K9 K10 STRUK CAN PELLET MATD BNUE FRHOL FAL PHA BKL BKS CNUE TCR TPL CCCL CNN1 CNN2 CN1 CN2 CN3 CH21 CH22 5 NKKN 50 SMIN RLA RLE ZSLUG 50 NAME OF STRUCTURE MATERIAL IN MAPLIB EF Ge 74988 NAME CLADDING MATERTAL IN MAPLIB NAME OF FUEL IN MAPLIB E G UPUO CONSTANT POISSON NUMBER OF FUEL DENS ITY OF FLUID FUEL AT MELTING TEMPERATURE KG M 3 LINEAR EXPANSION COEFFICIENT CF FLUID FUEL 1 DEG COMPRESSION MODULE OF FLUID FUEL 27 12 COMPRESSION MODULE OF SOLID FUEL 13E 12 POISSON NUMBER OF CLADDING MATERIAL ISOTHERM FOR OUTER BDUNDARY OF COLUMNAR FUEL DEG C 1700 ISOTHERM FOR OUTER BOUNDARY OF EQUIAXET FUEL DEG 1300 N CK 2 N CM 2 CONST
41. KFK 2508 c ie Be gt x si tcc 3 65 Z Zu lt 22 m c m o o 275 o o oc UE s O o a Y d 2c o o 5 5 gt z ESA j Als Manuskript vervielf ltigt F r diesen Bericht behalten wir uns alle Rechte vor GESELLSCHAFT F R KERNFORSCHUNG M B H KARLSRUHE KERNFORSCHUNGSZENTRUM KARLSRUHE KFK 2508 Institut f r Neutronenphysik und Reaktortechnik Projekt Schneller Br ter KINTIC 2 User s Manual L V th Gesellschaft f r Kernforschung mbH Karlsruhe Abstract KINTIC 2 is a two dimensional reactor dynamics program which can be used to analyze operational reactor transients or transients caused by accident situations In the near future it will be mainly used for the calculation of the predisassembly phase of sodium cooled fast reactor hypothet ical accidents Reactor kinetics may optionally be calculated with a simple point kinetics model or the adiabatic normal or improved quasistatic method The thermodynamics and ma terial motion part which was adapted from the CAPRI 2 system uses representative coolant channels in a single channel model It treats various phenomena which occur in intact fuel subassemblies One phase steady state and tran sient heat transfer and coolant pressure distribution pin deformation and failure sodium voiding slumping and fuel coo
42. LIB DISP SHR KSIOX DBN KINPUT TYP CARD PM K INPRM CHCKI 3 27 1 CHECK 3 2 26 1 1 0 O GO SM KINTIC ML 3 70 Literature 1 2 3 4 5 6 7 8 9 L V th Calculation of Group Constants for Use in the Two Dimensional Dynamics Code KINTIC 2 KFK 2289 1976 H Bachmann S Kleinheins Kurzes KAPR S Benutzer handbuch KFK 2317 1976 U Schumann MAPLIB Ein Programmsystem zur Bereit stellung von Stoffdaten f r Rechenprogramme KFK 1253 1970 L Mayer H Bachmann KINTIC 1 A program for the calculation of two dimensional reactor dynamics of fast reactors with the quasistatic method KFK 1627 1972 D Struwe P Royl P Wirtz et al CAPRI A computer code for the analysis of hypothetical core dis ruptive accidents in the Predisassembly Phase CONF 740401 p 1525 1974 L Calderola A theoretical model for the molten fuel coolant interaction in a nuclear fast reactor Nucl Eng Design Vol 22 p 175 1972 P Wirtz Ein Beitrag zur theoretischen Beschreibung des Siedens unter St rfallbedingungen in natrium gek hlten schnellen Reaktoren KFK 1858 1973 G Angerer Transport von Kernmaterialien w hrend Unf llen in Schnellen Natriumgek hlten Brutreaktoren Slumping KFK 1935 1974 B Kuczera Simulation of the transient behaviour of LMFBR fuel pins under consideration of special burnup phenomena using the BREDA II model Nucl Eng Design Vol 31 p
43. MBER OF AXIAL NODES IN CORE AND BLANKET LE 2D NUMBER AXIAL NODES IN UPPER AXIAL BLANKET NJMBER OF AXIAL NODES IN LOWER AXIAL BLANKET NUMBER OF AXIAL NODES IN FISSION CAS PLENUM NUMBER OF RADIAL ZONES IN THE PIN 1 19 CINSTANT NUMBER OF DIFFERENT KINDS OF PINS PARAMETER FOR SPACER IN CHANNEL Is 5T 0 NUMBER DF RIBS FOR SPIRAL WIRE CN PIN PERIMETER LT D HONEYCOMB GRID AS SPACER KIND OF PIN IN CHANNEL I CONSTANT CONSTANT DS NUMBER OF UNIT FOR PLOTTING NE 22 24 25 0 NO PLOT NUMBER TIME STEPS PER FULL PRINT BEFORE BOILING NUMBER OF TIME STEPS PER FULL PRINT AFTER BOILING DS NUMBER OF UNIT FOR PLOT OF BOILING PATTERN NE 23 24 25 0 NO PLOT 0 AXIAL CORE EXPANSICN 1 WITH AXIAL CORE EXPANSION PARAMETER FOR DETAILED PRINT DURING BCILING 0 NO DETAILED PRINT 1 SHORT OUTPUT AT EVERY TIME STEP 2 21 PRINT OF INTERNAL TIME STEPS 9 NO MECHANICAL STRAINS FOR REFERENCE TURES 1 NO MECHANICAL STRAINS FOR STEADY STATE TEMPE RATURES 1 AXIAL ITERATION SUBSTITUTE FOR SHEARING FORCE J3 NO AXIAL ITERATICN 1 AXIAL ITERATION OF PRESSURE 9 NO AXIAL ITERATION 1 BURNUP EFFECTS ARE ACCOUNTED FOR 9 OTHERWISE PARAMETER FOR DETAILED PRINT IN BCILING ROUTINE IN CASE OF ERRORS 0 NC ADDITICNAL PRINT 1 2 3 DIFFERENT LEVELS OF ADDITIONAL CUTPUT SLUMPING CRITERION IN CHANNEL I J CLADDING TEMPERATURE TCSLB AND FUEL MELT K5 K6 KT K8 MMLSB 1
44. N WITH CAPRI 2 THERMODYNAMICS SINCE HAS BEEN DEVELOPED FROM THE INPUT FOR THE CAPRI 2 STAND ALONE VERSION A FEW EXPLANATIONS CONCERNING THE DIFFERENCES ARE IN ORDER THESE ARE USEFUL ESPECIALLY FOR PERSONS WHO WISH TO RUN THE TWO CODES PARALLEL OR WHO WANT TO CCNVERT AN FOR THE CAPRI 2 SYSTEM INTO THE BLOCK THEIN TO FACILITATE THIS CONVERSION THE INPUT HAS NUT BEEN MODIFIED AS FAR AS POSSIBLE THE CATA IN THE BLOCK THEIN HAVE THE FOLLOWING ORDER 1 GLOBAL INTEGER DATA PRECEDED BY THE CONSTANT GLCBINT 2 GLCBAL REAL DATA PRECEDED BY THE CONSTANT GLOBREAL 3 CHANNEL DATA THE DATA FOR EACH CHANNEL BEING PRECEDED BY THE CCNSTANT CHAN AND THE NUMBER OF THE CHANNEL THE ORDER OF CHANNELS IS ARBITRARY THE END OF THE BLCCK THEIN IS SIGNALED BY THE CONSTANT END AMONG THE MANY GLOBAL DATA TO BE PROVIDED FOR CAPRI 2 SYSTEM ONLY A FEW NEED BE DEFINED FOR THE CAPRI 2 THERMODYNAMICS MODULES THEREFORE THE GLOBAL INPUT WAS NEWLY FORMULATED THE DATA WERE GROUPED INTO SMALL DATASETS BEING PRECEDEC BY CONSTANTS NODE CEOM IN BLOCK OF GLOBAL INTEGERS THE DATASET NODE MUST BE THE FIRST ONE WHEREAS THE ORDER OF THE OTHER TWO SETS IS ARBITRARY AS IS THE ORDER DF ALL SETS IN THE BLOCK OF GLCBAL DATA A SET MAY BE OMITTED IF IT CONTAINS ONLY ZEROS OR DEFAULT VALUES THE CHANNEL INPUT WAS NOT REFORMULATED IT IS UNFORMATTED BUT SINCE FORMATTED INPUT IS UNDER CERTAIN CONDITIONS
45. NIT 3330 VOL SER TSTLIB DISP NEW KEEP 1 K FT23F001 DD UNIT SYSDA SPACE ITRK 10 K FT25F001 DD DSN T1G30Z TI INNN UNI T3330 VOL SER TSTLIB DISP SHR K FT26F001 DD DSN CO ITINNN UNIT 3330 VDL SER TSTLIB DISP S NEW KEEP SPACE ITRK 35 K SYSIN DD KSIOX DBN KINPUT TYP CARD PM KETT START 1 1 12 1281 6 6 1 120 23 0 PERTUR 1 1 11101 19 520 le le O DCN 5 41310 44730 4 88 2 0 49940 4 19 12 5 O CCNTROL O 1 0 5 5 527 4 005 00001 201 OOl el POWER 800 CHECK 3 1 26 15 1 01 x KSIOX DBN FEEDBC TYP CARD PM KETT 2 1 0 12 1 2 12 24 3 2 2 4 2 2 0 KSIOX DBN THEIN TYP CARD PM KINPRM GLOB INT NCDE 221 12 22 6 6 1 l i 11 CNT1 0 21 1 19 109 1911209330002 22201000 GLOBREAL CNT2 5 10 10 50 2 10 50 50 1 110 1 10 0 5 OPER 9 8545 1 8145 0 0 0 377 750 300 MAPL NAL 14981 14981 UPUO 276 8740 24 4 2T 12 13 12 3 1700 1300 CCOL 9 7 286 498 498 0 133 2 2 10 015 2 005 2 1 1 1 5 02 CHAN 1 1 21 21 2 55 3 31 21 21 38 3 61 21 18 4 24 55 3 34 59 39 9 3 91 21 6 63155 3 12 28 2 4342 2 121 21 6 1 35 5 12 61894 5 3 1 2284 5 151 21 21 7 4 181 21 6 109166 25 151833 7 12 122998 2 2009 083 217 225 211 9 40221 097239 106798 0086788 097401 31256 081903 225 1 14 231 3 80000 1 10 124 8 234 12 45 15 1 30415 2 05 15 2 63 15 3 38 15
46. OF A SUBZONE K24 K26 THEN K27 M 4 NV A 4 MDC1 NJMBER OF FIRST COMPOSITION PERTAINING TO THE VARIANT OF A SUBZONE MDC2 NUMBER OF LAST COMPOSITION PERTAINING TO THE VARIANT OF A SUBZONE MSU SUBZONE NUMBER NVA 9 VARIANT OF A SUBZONE DENSITY AND VOLUME FRACTION OF NVA MACRO MATERIALS ARE CHANGED 0 OTHERWISE FOR NVA GT O CONTINUE WITH K26 OTHERWISE 523 MANAV T NAME OF MACRO MATERIAL THE CONTENTS WHICH IS TO BE CHANGED RHOI NEW DENSITY 6 3 VF 1 NEW VOLUME FRACTION I 1 NVA CONTROL CONSTANT NIT NUMBER OF ITERATIONS OF SHAPE FUNCTION NORMALLY 0 K ZERO 0 QUASISTATIC METHOD PDINT KINETICS NORMAL QUASISTATIC METHOD 1 ADIABATIC METHOD MPROVED QUASISTATIC METHOD 1 KQB 9 1 528 K29 K30 531 K32 533 K34 K35 536 EPSI EPS2 EPS3 EPS4 1 Iz1 2 NV 55 1 T 1 2 NV IF NO EXTERNAL REACTIVITY IS TO BE USED K30 RORAMP NRO TRO II T 1 NRQ RO T I 1 NRO POWER XP 40 LOWER LIMIT FOR ACCURACY TEST IN POINT KINETICS MODULE 1 5 UPPER LIMIT FOR ACCURACY TEST IN POINT KINETICS MODULE 1 E 4 MAXIMUM DEVIATION INTERVAL MAXIMUM DEVIATION REACTIVITY RHO LIFETIME L AND EFFECTIVE BETA I AT END OF NORMAL INTERVAL ORDER EPS4 RHO ABSOLUTE VALUE EPS4 L RELATIVE VALUE 5 1 EPSA BETA 20 9es RELATIVE VALUES MAXIMUM ALTERATION OF RHO Ly AND BETA I IN SINGLE ZONE DURING ONE MAC
47. RCE ACTING GN FUEL ELASTIC CONSTANT OF SPRING FRACTICN OF POWER RELEASED COLUMN N UN IN FUEL FRACTION OF POWER RELEASED CLACCING FRACTION OF POWER RELEASED IN COOLANT FRACTION MATERIAL OF POWER RELEASED IN STRUCTURE MATERIAL DATA M M M e EXPLANATION MAXIMUM HEAT TRANSFER COEFFICIENT GAP BETWEEN FUEL AND CLADDING W M DEG GAP PARAMETER FOR CALCULATING A VARIABLE HEAT TRANSFER COEFFICIENT W MXDEC H BOND MINCBONDP DBOND BOND PELLET DENSITY RELATIVE TO THEORETICAL DEN SITY FOR EACH NODE PELLET DENSITY RELATIVE TO THEORETICAL DEN SITY IN COLUMNAR GRAIN ZONE FOR A ONE ZONE C 486 515 516 Eo CNPU I I 1 NM2 FPSGO 53 MODEL LET DPOLI DPPLUT MOL CONCENTRAT ION OF PU IN FUEL STATIC PRESSURE IN FISSION GAS PLENUM 2 SLUMPING INPUT POSITICN CONTENTS 521 522 523 524 526 527 528 529 Fo FNY FXII FFUEL FCLAD FQF FG FMSLB TCSLB SPLSLB FCI INPUT POSITIGN CONTENTS 530 531 532 533 534 536 537 538 539 540 Ge SPLFCI RCFCI FMFCI RFRAG TAUM XIW EPSFCI HWEGF FL IQ VBRKU RADIAL HEAT EXPLANATION KINEMATIC VISCOSITY OF FUEL CLADDING MIXTURE 2 5 01 FRICTION COEFFICIENT 23 FOAMING EFFECT I INCREASE OF VOLUME DURING MELTING OF FUEL 1 0 FOAMING EFFECT OF CLADDING 1e DEGREE BY WHICH CROSS
48. RO INTERVAL ORDER AND DIMENSIONS AS ABOVE RECOMMENCED VALUES FOR FAST REACTORS EPS5 RHO 001 55 1 5 5 el OF REACTIVITY AT ENC GF MACRO OTHERWISE K29 CONSTANT I NUMBER OF POINTS AT WHICH REACTIVITY IS GIVEN 1 6 TIME TROL1 GT O SEC REACTIVITY AT TIME TRD I CONSTANT STATIONARY REACTOR POWER MW FOR CHECKPOINT CONTINUE WITH K34 OTHERWISE K32 ENDE 3 CONTINUE CHECK NCHEC MAKMAX NBCH FOR A RESTART CASE END OF BLOCK CONSTANT WITH K35 CONSTANT 0 NO CHECKPOINT 1 CHECKPOINT AFTER MAKMAX STATICNARY SHAPE FUNCTION ITERATIONS 2 CHECKPOINT AFTER FINAL STATIONARY THERMO HYDRAUL ICS 3 CHECKPOINT AFTER MAKMAX MACRO INTERVALS 4 CHECKPOINT BEFORE RECALCULATICN OF NEXT START OF CALCULAT ION FIRST MACRC INTERVAL NCHEC 1 NUMBER OF STATIONARY ITERATICNS THOSE UF FOREGOING RUN INCLUDED MAKMAX 1 FOR CHECKPOINT BEFORE FINAL STAT IONARY SHAPE FUNCTION CALCULATION NUMBER OF MACRO INTERVALS BEFCRE CHECK POINT THOSE OF FOREGOING RUAS INCLUDED NCHEC 3 DS NUMBER OF RESTART FILE NE 23 24 25 OTHERWISE K37 41 CONSIS CONSTANT KONSI 0 0 STATIONARY CONSISTENCY ITERATION FOR ONLY 1 CONSISTEMCY ITERATION FOR GROUP CCNSTANTS FOR NFEED NE O ONLY 1 CONSISTENCY ITERATION FOR GROUP CCNSTANTS AND DENSITIES FOR NFEED GT O ONLY KONE 0 NO STATIONARY CRITICALITY SEARCH 12 CRITICALITY SEARCH WITH OPTIONS OF KIN
49. SIN DD KSIOX DBN KINPUT TYP CARD PM KETT START 118 7215 61 122 23 0 PERTUR 2 13 30 2 14 2 0 10 1 4 BRENN KUEHL 2 O 1 10 1 1 CCN 2 12410 amp 5 8 3 O CONTROL O 1 O 1 5 1 4 0001 90001 Ol 4 01 0004 el RORAMP 2 el o2 5 POWER 400 6 CHECK 3 3 26 CCNS 15 1 9 1 KSIOX DBN FEEDBC TYP CARD PM KINPRM 15600 71411 l 206 3 262 2038 645 935 20 005 310 380 1 00 0 2700 1400 1000 1430 542 542 8 9 0 0 8 9 7 7 0 7 7 084 00 84 7 7 0 7 7 067 0 0 067 12 0 0 12 3 O 0 3 12 O 0 12 2484 0 0 24 3 00 3 9 6 3 O 0 9 6 3 05 0 1 1 465 036 06 9 098 1 1 11 1 1 12 9 6 21 5 6 21 5 6 9 12 9 6 21 5 6 21 5 6 9 3 5 KSIOX DBN DX LDIM TYP CARD PMN KETT 12 6 8 KSIOX DBN DXDIF TYP CARD PMN PRDIXY DIXY 00 14 221 300100900 201 000 CN 6 2 0205 3 7104 1 10 REGN 0 5 1 3 19 12 1138 10 213 31335 61313 7361012 436 HSTP 0 5 2 2 25 3 70 VSTP O 11 160 2 125 2 100 3 60 2 35 2 0 DXNF 0 G0 SM KINTIC MU 3 67 CASE C ass JOBCARD ses REGION 440K T 3 FORMAT PR DDNAME FT42FOOL EXEC KSG IK FT44FOOL DD SPACE 13064 210 IK FTOLFOOL DD DUMMY K FT20F8001 DD DSN A2 LIINNN UNIT 3330 VOL SER TSTLIB DI SP UNEW KEEP SPACE TRK 2 K FT21F001 DO DSN A3 IIINNN UNI T 3330 VOL SER TSTLIB DISP INEW KEEP SPACE ITRK 2 K FT22F001 DD DSN A4 ITIINNN U
50. TIC 2 EPS 6 MAXIMUM DEVIATION OF STATIONARY K EFF FROM le S38 END OF BLOCK K39 DESCR CONSTANT 540 END OF BLOCK 42 6 2 INSTIT M m TO BE PROVIDED ONLY FOR START OF A CALCULATION IF KCNE NE O IN BLOCK KINPUT KAPROS CONTROL CARD KSTOX DBN INSTIT TYP CARD PM KINPRM CONCATENATION SHOULD BE USED SEE BLOCK KINPUT CONTENTS OF BLOCK Kl RADIT IF K EFF IS TO BE CHANGED BY ADJUST ING REACTOR DIMENSIONS NOT TO BE USED TC GETHER WITH CAPRI 2 THERMODYNAMICS MATIT IF K EFF IS ADJUSTED BY CHANGING COMPOSITIONS S2 FOR ANAZ RADIT CONTINUE WITH GTHERWISE ALPHI HSTP IF HORIZONTAL REACTOR AXIS IS TO BE CHANGED VSTP IF VERTICAL REACTOR AXIS 15 TO BE CHANGED FACTI INITIAL REACTOR DIMENSION L IS VARIED BETWEEN L FACTL AND L FACTI S4 END GF BLOCK K5 NNMI NUMBER OF COMPOSITIONS TO BE CHANGED THEIR NUMBERS IN DIXY ZONE INPUT I 1 NNMI MANAL NAME OF FIRST MACRO MATERIAL TO BE CHANGED MANA2 NAME OF SECOND MACRO MATERIAL IF NO SECOND MATERIAL IS TO BE USED MANA2 VACUUM FACT2 VOLUME FRACTION OF FIRST MACRO MATERIAL IS VARIED BETWEEN VF FACT2 AND VF FACT2 SECOND MACRO MATERIAL FILLS UP PROVIDES THE SPACE PROVIDED FILLED UP BY THE FIRST S6 END OF BLOCK 43 6 3 BLOCK FEEDBC eM MY M TO BE PROVIDED ONLY FOR START OF CALCULA
51. TIMATE OF RADIAL TEMPERATURE DIFFERENCE IN THE PELLET DEG C K5 EPSK VKUEL TK IN ANTB ANTC ANTK ANTS TSBR TSCL TSKUE TSSTR UMELT UREKR 44 ERROR LIMIT FOR ITERATIGN TEMPERATURES DEG C RECOMMENDED VALUE 01 COOLANT VELOCITY CM SECI TEMPERATURE DF COOLANT AT ENTRY DEG C FRACTION OF HEAT RELEASED IN FUEL FRACTION GF HEAT RELEASED IN CLADDING FRACTION OF HEAT RELEASED IN COOLANT FRACTION OF HEAT RELEASED IN STRUCTURE MATERIAL MELTING TEMPERATURE OF FUEL DEG C MELTING TEMPERATURE OF CLADDING DEG C BOILING TEMPERATURE OF COCLANT DEG C MELTING TEMPERATURE OF STRUCTURE MATERIAL DEG C LATENT HEAT OF MELTING FOR FUEL CAL CN 3 LATENT HEAT OF RECRISTALLIZATION FOR FUEL CAL CM 3 THIS PART OF THE INPUT CONTAINS THE TEMPERATURE CEPENDENT THERMODYNAMICS PARAMETERS IN THE FORM 1 4 THE AC TUAL PARAMETER IS CALCULATED FROM THESE VALUES VIA 1 2 T4 P 3 T T P T P 4 WHERE TLIMIT IS ONE OF THE VALUES TSBR TSSTR DEPENDING ON WHICH MATERIAL P REFERS TO T LE TLIMIT T GT TLIMIT TSCL TSKUE OR TFE TRANSFER COEFFICIENTS HBC AND HCK DEPEND ON THE TEMPERATURE OF FUEL AND CLADDING 1 1 4 4 1 1 4 ROS T I 1 4 CPB I 12154 1 1 4 1 1 41 CPS I 1514 HBC I I 1 4 HCK I I 1 4 XLB I I 1 4 XLC I I7154 RESP FUEL DENSITY G CM 3
52. TION KAPROS CONTROL CARD KSICX CBN FEEDBC TYP CARD PM KINPRM CONCATENATION SHOULD BE USED SEE BLOCK KINPUT CONTENTS OF BLOCK S1 FOR NFEED GE O K2 511 OTHERWISE S12 K13 K2 NKKN NUMBER OF RADIAL SEGMENTS FOR THE DEFINITION CF COOL ANT CHANNELS 0 1 105 NKKD IN BLOCK KINPUT NM NJMBER OF AXIAL ZONES PER SEGMENT Oe LE NM LE 10 NMD IN BLOCK KINPUT NNMAX MAXIMUM NUMBER OF RADIAL ZONES IN FUEL PELLET O LE NNMAX LE 6 NNMAX IN BLOCK KINPUT 0 CONSTANT NVC IN 1 VOLUME CHANGES ARE TAKEN INTO ACCOUNT 0 OTHERWISE NPR INT CONTROLS OUTPUT IF THERMODYNAMIC S AND FEEDBACK MODULES IF NAUS IN BLOCK KINPUT NE O0 AND eNE 1 0 NO OUTPUT 1 OUTPUT AT END OF PERTURBAT ION INTERVAL 2 SHORT OUTPUT FOR EACH ITERATICN OF NORMAL INTERVAL 1 LONG OUTPUT FOR EACH ITERATICN OF NCRMAL INTERVAL NSTUE NUMBER OF AXIAL ZONE CONTAINING THE SPACERS NFEED NFEED IN BLOCK KINPUT 0 NO FEEDBACK 1 OLD VERSION OF THERMODYNAMICS 1 CONSTANT 53 FOR NFEED I END OF BLOCK FOR NFEED 1 K4 FOR EACH RADIAL CHANNEL THEN S8 K4 KKN NUMBER OF CHANNEL VSTRUK VOLUME OF STRUCTURE MATERIAL PER CM LENGTH OF PIN ICMxx2 NN NUMBER OF RADIAL ZONES IN PELLET 2 RBR PELLET RADIUS CM DCLAD CLADDING THICKNESS CM RKUE EQUIVALENT RADIUS OF COOLANT CHANNEL CM VDUF FOLLOWING QUOTIENT VOLUME OF STRUCTURE MATER IAL PART OF I TS SURFACE IN CONTACT WITH COOLANT CM DELTB ES
53. ally the restart data set is updated every time a potential checkpoint is encountered during the flow of calculations and a message is printed In the case of an abnormal job end the job can be restarted from the last of these internal checkpoints If the re maining CPU time for writing the restart file may be too small KINTIC 2 tries to produce a restart file on unit 24 in order to avoid destroying the existing restart file If a DD card for unit 24 has been submitted by the user and the CPU time is sufficient this file may be used for a restart otherwise the normal restart file is to be used which of course contains the data of the last but one checkpoint 3 4 The evaluation files For a convenient evaluation of the results of a calcula tion KINTIC 2 produces up to 5 files containing time dependent results Production is optimal and may be Stopped continued or newly started after a checkpoint If at least one of these files is produced KINTIC 2 needs an additional intermediate file the number of which is defined in the initial input this number is in case a job produces no evaluation files automati cally put equal to zero thus requiring no DD card for the intermediate file in this case If evaluation files 26 are to be written by a restart job the foregoing job of which did not produce evaluation files the ds num ber of the intermediate file is assumed to be 23 and thus a DD card for this file is to be pr
54. and axial zone boun daries are to be repeated in the neutronics mesh In the example this rule concerns the position of column 2 and lines 13 and 14 Otherwise the neutronics mesh is only governed by the rulesprescribed by DIXY i e number of axial and radial points must be a multiple of 4 and 2 resp 4 6 Representation of control rods There are two ways of representing control rods which are treated as non feedback zones in KINTIC The first one has been implicitely depicted in the example al ready with a control rod zone inserted between the thermodynamics zones A second pressibility consists in mixing the control rod follower zones with a feedback channel In this case no extra radial segment is defined for the control rod Instead the user has to specify that a certain amount of control rod or follower material is to be mixed with the zones pertaining to one feedback channel For example if the control rod fuel element ratio is 1 5 1 6 has to be specified in the input Internally the formalism for a time dependent replacement of one material by another is used for this kind of simulation and the cor related input therefore turns up among the input defining the external perturbation It is not possible at the moment to simulate control rod movement for control rods represented in this second way 4335 5 Job control language The following job control language cards are to be provided for a KINTIC job Job
55. ants per feedback zone to be used for the actual calculations The new thermodynamics modules allow a treatment of up to 30 representative coolant channels with up to 20 axial zones in the core and blanket region and additional axial zones above and below If all zones were used for treating the feedback this would re sult in up to 900 zones and even if only the zones containing fuel were used up to 600 feedback zones would result From a neutronics point of view the zones outside the blanket need not be correlated with the thermodynamics zones In addition the axial and radial representation of feedback often need not be as accurate as the thermodynamics e g adjacent radial channels differing only in burnup may be collapsed for the feedback representation This is necessary since the block of macroscopic group con stants for 600 zones is unmanageably big The number of feedback and non feedback zones has therefore been restricted to 200 feedback zones may be col lapsed axially radially and azimuthally from the thermodynamics zones One therefore has four geometrical representations of the original reactor configuration The subzone representation concerning the macroscopic group constants the thermodynamics representation the feedback representation including non feedback zones the neutronics mesh 28 Of course these meshes are correlated In the following sections each of the meshes will be discussed
56. card a F RMAT DDNAME FT42F001 EXEC KSG K FT44FOO1 DD SPACE 3064 ms1 b K FTyyFOO1 DD DUMMY c K FFxxFOO1 DD K FT23FOO1 DD e K FT24FOO1 DD K FT25FOO1 DD g K SYSIN DD Kintic input blocks see following chapter G SM KINTIC Comments a Region and time parameters are very much a function of the case to be calculated The minimum region small test cases with KAPRST O is currently about 320 K for the old thermodynamics 460 K for the new thermodynamics A user lacking experience may start his case with a 480 K region and then adjust the region using the messages printed at the beginning of the job Times are 1 5 minutes for small test cases and several hours for production runs check points should be used in the latter case b Not to be provided for small test cases only For cases using the new thermodynamics msl may be up to 3000 c d e g 34 To be provided for the new thermodynamics only if KAPRML 6 see block THEIN This is the DD card for the MAPLIB dataset Chapter 3 2 If MAPLIB messages are to be printed seperately DUMMY is to be replaced by the specifications for a dataset and a corresponding FORMAT card is to be inserted DD cards to be provided for the up to 5 evaluation datasets KTP UT of block INPUT and ICLCMP NFCIPL IV ID NSPLT of block THEIN the intermediate eva
57. core has been short ened axially the original core height is given by the dashed lines This anticipates the neutronics represen tation which needs only a reflector thickness of a few neutron mean free paths for accurately representing the flux at the outer blanket boundaries Thus excessive axial height needed for the thermodynamics representa tion may be trimmed away for the neutronics There are no restrictions imposed on the choice of subzones apart from the fact that they must reflect the material compositions On the other hand the choice of the other meshes is influenced by the subzone division through rules to be defined in the following sections The user should therefore always keep in mind the necessities arising from the thermodynamics and feedback represen tation even at the stage where only the group constants are to be determined This is particularly true if an artificial boundary like the one between subzones 4 and 5 is introduced since such a boundary later influences the possible thermodynamics representations 4 3 Geometry for thermodynamics Fig 6 shows the geometric representation of the reactor for thermodynamics Here the full axial height of the core is used but radially the absorber and reflector regions are not included 7 radial channels with 14 axial zones are used 9 axial zones comprise the core and blanket region The following rules have to be obeyed for the thermo dynamics mesh b
58. d einige Informationen zur Codeorganisation und zur geome trischen und thermohydraulischen Darstellung des Reaktors Der wesentliche Teil besteht aus Ein und Ausgabebeschrei bung sowie Testf llen KINTIC 2 l uft im KAPROS System und ist seit Mitte 1976 verf gbar Contents 1 Introduction 2 Physics of the KINTIC 2 system 2 1 2 2 2 3 2 4 2 5 2 6 2 7 Nuclear data Calculations for the stationary reactor Neutron kinetics Thermodynamics and material movements initiated by the transient Feedback External perturbation Time step automatization and iterative procedure Organization of the code system KINTIC 2 3 1 3 2 3 3 3 4 Modules and data organization MAPLIB messages The restart option The evaluation files Geometrical representation of the reactor 4 1 Introduction Geometry for group constants Geometry for thermodynamics Geometry for feedback Geometry for neutronics Representation of control rods Job control language Input 6 1 6 2 6 3 6 4 6 5 Block KINPUT Block INSTIT Block FEEDBACK Block THEIN Restrictions concerning input blocks for DIXY e UU U 13 13 15 21 21 24 24 25 26 26 28 29 30 31 32 33 35 37 42 43 47 55 Output Sample cases Literature Figures II 56 59 70 72 1 Introduction With prototype fast breeder reactors being built or in operation and planning proceeding to big fast reacto
59. ed by 1 2 the lower limit for the step length is 1077 the stability criterion are user determined with recom Sec Upper and lower limits for mandations as to their values included in the input description A number of micro steps is joined together to form one normal step After each micro step a number of criteria are checked to determine whether the end of a normal step has been reached These are al a2 a3 a4 a5 end 17 Reactivity criterion If Pi is the reactivity at the start and Pr that at the end of the amplitude calculation and Max pj do o the amplitude calculation is stopped if dp gt 5 and p lt 8 or dp gt 2 and 8 lt p lt 95 or dp gt 1 and 95 lt p Time criterion A prescribed normal interval may be used the prescription resulting from thermodynamics or convergence considerations see below In addi tion if the amplitude has changed by more than 10 the amplitude calculation is stopped when the inter val length exceeds 106 lifetime 1 1 being the prompt neutron Minimax criterion The normal interval ends when the amplitude reaches a minimum or maximum This criterium is not checked as long as the change in amplitude stays below 10 Amplitude criterion The change in amplitude must not exceed a factor of 10 Slope criterion The time derivation of the amplitude must not change by more than a factor of 2 This criterion
60. f original configuration mesh point o 80 L T 866 6 2 T 666 661 Ku 5666 666 66 000705 IdWU M 00070 0 375 0 300 0 225 TIME CSEC 0 075 0 000 FIG 9 CASE B AMPLITUDECT 81 FIG Tode 10 CASE B RERCTIVITYCOT TOTAL REACTIVITY DOPPLER o A FUEL Ae e CLAD a x CE STRU 1 219 s gt 2 B E ZIN I 8 CI 2 OS 5 3 0 000 0 075 0 150 0 225 0 300 1 0 375 e N 00 0 00 0 00 0 00 0 00 0 00 07 Fer 82 00070 00070 00070 00070 00070 0 300 25 0 150 I 0 075 0 000 00070 CASE LIFETIMEC TJ AND BETAC TJ 11 FIG 83 00070001 0007008 0007009 000 00 0007002 ddMOd LO 0 150 AT s 0 075 EE 0 000 00070 12 CASE POWERCT FIG 84 80 000 100 000 40 000 60 000 ENS cub 20 000 0 000 Hem AXIAL INTEGRAL OF POWER T T 0 000 0 075 0 150 0 225 0 300 0 375 UNE DOC J FIG 13 CASE B AXIAL INTEGRAL OF POWER 85 125 000 1 x10 50 000 75 000 100 000 25 000 MAXIMUM POWER CW 0 000 1 T I 0 000 0 075 0 150 0 225 0 300 0 375 rule BSEC FIG 14 CASE B MAXIMUM POWER IN PIN
61. g 1 Flow chart of steady state part of KINTIC 2 73 Calculate time dependent am plitude for nor mal step AIREKI Calculate new shape function for adiabatic method resp solve homogeneous problem for quasistatic method DXDIFF Feedback Calculate transient thermohydraulics and material motion feedback INSTEM or STATI ITC1 ITCB BREDA FSLUM FCIKU Calculate new shape function using source from homogeneous problem as first estimate DXDIFF Calculate reactivity with new form Make changes function EVA Normal to normal step sufficient gt 1 step incorpo iterated rate better estimates Calculate transient group constants QSUM and reactivity at end of normal step EVA Iteration of macro step necessary Prepare data for next normal step ndo lt problem gt no yes lt inner outer iteration gt Fig 2 Flow chart of transient part of KINTIC 2 Initialize new macro step neutronics thermo dynamics external perturbation P macro step gt step izi ie imicro step t 0 d step for coolant flow 1 0 external perturbation interval step for fuel temperatures Fig 3 Interaction of time scales in 2 t end of normal interval de end of macro interval outer _ iteration inner
62. ial material compositions and or collapsing spectra Small differences in initial material composition or collapsing spectrum need not be taken into account the degree of sophistication is determined by the user Typically a few subzones 10 15 are sufficient For example subzones would be The different enrichment zones of the core upper and lower axial blanket zones taken together the inner and the outer radial blanket seperately for treating the change of spectra etc As is obvious from this example subzones need not be geometrically coherent An illustration of this example is given in fig s 4 and 5 All nuclear data needed for such a subzone i e group constants including their dependence on possible changes of composition and on temperature and data of delayed neutrons are compiled in the programs for calculation of group constants for KINTIC 2 to be run ahead of KINTIC and described in 1 They are collected on a file which is input for KINTIC 2 Apart from this file the user has to provide the code with the information as to which geomet rical zone belongs to which subzone For the first steady State neutronics calculation each zone has the original composition of the subzone to which it belongs Alternately slight alterations of the original compositions may be defined in order to e g take into account steady state axial sodium density variations Normally this option need not be used since the dens
63. integration of the corresponding modules ie 2 5 Feedback Feedback effects are of course accounted for in KINTIC 2 only if the thermodynamics modules are used The following feedback effects are treated a Temperature dependent changes of group constants i e Doppler effect Only the fuel capture and fission group constants are changed For more details see 1 b Temperature dependent changes of density and volume fractions of fuel cladding coolant and structure material Changes of microscopic group constants due to changes in composition can optionally be accounted for 1 c For the old thermodynamics models optionally axial and radial core expansion for the new thermodynamics optionally axial core expansion d For the new thermodynamic models gross material move ments resulting from voiding slumping or fuel coolant interaction Again changes of microscopic group con stants due to changes in composition be accounted for Smeared densities are used for simulating material movements affecting only part of a zone 2 6 External perturbation The description of the external perturbation has been changed basically together with the concept for the group constants Instead of using rather abstract differences of compositions for the definition of the external pertur bation the user may now describe the perturbation in a more direct way The external perturbation may originate either in the thermody
64. ity distributions are automatically adjusted to the thermodynamics results during the steady state consistency iteration to be des cribed bel w 2 2 Calculations for the stationary reactor Apart from determining the steady state neutronics and thermohydraulics the calculations for the stationary reactor must achieve the following two objectives a Zero initial reactivity b Consistency of temperature field densities and volume fractions and group constants In the case of a calculation without feedback the second Objective is omitted The first objective may be reached in a number of ways There are options for criticality search provided by KINTIC 2 as well as the diffusion module DIXY 13 In the case of calculations with the new thermodynamics modules some restrictions are placed on the use of these options which are specified in the input description Whether or not criticality search is used the remaining nonzero reactivity is eliminated by dividing all group constants containing v the number of neutrons per fission by kore By this opera tion fictitious transients arising from nonzero stationary reactivity are avoided The second objective is reached by iterating the neutron field and the temperature material density field until consistency is achieved This is done automatically by the program With the old thermodynamics two iterations are sufficient to reach consistency whereas for the CAPRI 2 thermod
65. lant interaction The report gives a short summary of the underlying physical models and some information on code organization and geometrical and thermohydraulic represen tation of the reactor The main part consists of input and output description and sample cases KINTIC 2 works in the KAPROS system and is operational since mid 1976 KINTIC 2 Benutzerhandbuch Zusammenfassung KINTIC 2 ist ein zweidimensionales Reaktordynamikprogramm das zur Analyse von Reaktorbetriebstransienten oder von Transienten die durch St rfallsituationen hervorgerufen werden eingesetzt werden kann In n chster Zeit wird es im wesent lichen zur Berechnung der Einleitungsphase hypotetischer St rf lle bei Natrium gek hlten schnellen Reaktoren benutzt werden Zur Berechnung der Reaktorkinetik kann wahlweise ein einfaches Punktkinetikmodell oder die adiabatische die nor male oder die verbesserte quasistatische Methode herangezo gen werden Der Programmteil zur Berechnung der Thermodynamik und Materialbewegung der von dem CAPRI 2 System bernommen wurde verwendet ein Einkanalmodell mit charakteristischen K hlkan len Er behandelt verschiedene Ph nomene die in intakten Brennelementen auftreten Einphasigen station ren und transienten W rmetransport und Druckverteilung Brenn stabdeformation und versagen Natriumsieden Slumping und Brennstoff Natrium Reaktion Der Bericht enth lt eine kurze Zusammenfassung der benutzten physikalischen Modelle un
66. luation file KPLI of block KINPUT the restart file NBCHI from block KINPUT which contains the data of the foregoing job and the new restart file NBCH from block KINPUT to be provided by the current job DD card for intermediate evaluation file for restart case with the foregoing job having no evaluation files Backup checkpoint file see chapter 3 DD card for dataset containing the group constants To be provided only for the start of a run 35 6 Input The card input to the code system consists of up to 7 input blocks which are listed below together with the conditions under which they are to be provided Name of block to be provided for KINPUT always INSTIT start of calculation with use of KINTIC critically search options FEEDBC start of calculation THEIN start of calculation with CAPRI thermo dynamics DX LDIM start of calculation DXDIF start of calculation DXBUCK start of calculation with nonzero buckling A description of the contents of the first four blocks will be given on the following pages The contents of the last three blocks is detailed in the input descrip tion of the KAPR S DIXY version and thus is not listed here but some restrictions on the input for DIXY arising from the use in conjunction with KINTIC 2 are given The contents of the four blocks is as follows KINPUT Basic control data for both start of a calcula tion or restart definition of perturbation of variants of s
67. n changes occuring at the onset of boiling or fuel coolant interaction Since the task of managing the time scales is by far too demanding for the user regu lation of the interaction of the different time scales and the choice of adequate step lengths is largely taken over by KINTIC and the CAPRI 2 modules A few parameters are left to the user for regulating the accuracy 16 The different interacting time scales belong to the following processes a Development of prompt neutron population b Thermodynamics Alterations of temperatures motion of one and two phase coolant other material motions initiated by the transient c Shape function alterations d External perturbation Apart from the external perturbation which is predeter mined all processes may require an interative treatment In the following the way this is realized is described using the above classification see also fig 2 and 3 a Calculation of the prompt neutron population i e the amplitude A from eq 4 is effected in so called micro steps employing the point kinetics coefficients given by eq 7 and an estimate on their time dependence The calculation is started with a step length of 10 sec and normally the step length is doubled after each step until either a maximum step length 2 1072 or a stability criterion is fulfilled If the amplitude starts to rise more rapidly the step length sec is is automatically reduc
68. namics or in the neutronics part of the program The following perturbations may be simula ted 14 a Origin thermodynamics The loss of flow situation may be simulated by simply submitting the coefficients of a function describing the time dependent decrease of pressure see K7 of block THEIN If this kind of perturbation is not present the coefficients must be zero The simulation is not possible with the old thermodynamics modules b Origin neutronics Material movement may be simulated for a number of different cases This is possible in conjunction with the old or new thermodynamics modules or without any thermodynamics Any movement of this kind may start and stop at any time Transient over power accidents may be simulated by some sort of ma terial e g control rod movement or by feeding in an external ramp As in the case of feedback gross material movement in part of a zone is simulated with smeared densities Since this is only an approximation zones affected by material movement should be kept sufficiently small to avoid large errors It is possible to simulate the following kinds of movement bO A dummy perturbation is provided with no material movement taking place Since new shape functions are calculated at the beginning and end of each time interval defining an external perturbation the dummy perturbation may be used to enforce shape function calculation at a certain time b1 Replacing one compositi
69. nd ent microscopic group constants and to define the ex ternal perturbations in a much more direct way The new concept has already been documented 1 Zum Druck eingereicht am Nov 1977 3 In order to facilitate a coupling with other codes KINTIC was broken up into a number of modules with one controlling module and integrated into the nuclear code system KAPROS 2 4 The parts concerning thermodynamics pin deformation fuel coolant interaction sodium boiling and fuel slump ing were taken out of the code system CAPRI 2 5 con verted into KAPROS modules and coupled to KINTIC Apart from the old thermodynamics modules which have been kept active as an option KINTIC is thus equipped with a more modern thermodynamics and material movement code which will constantly be updated with the newest versions available KINTIC thus has become a system of KAPROS modules which will grow in the future and which will be referred to as the KINTIC 2 system The main purpose of this document is to aquaint a future user of KINTIC 2 with the basic methods employed and pro vide him with the material input description and sample cases for running his own calculations It is not intended to compile the methods and formulas used since this is beyond the scope of this author many codes having been adapted from other authors a list of the literature available on e g the new thermodynamics and material movement modules is provided 6
70. ner iteration concerning the normal step which has been described above The number of inner iterations normally varies between 1 and 12 with most often 2 5 inner iterations The number of outer iterations is 1 i e no iteration or at most 2 i e one recal culation with 1 occuring for cases with no or weak feed back and no or insignificant material motions At the end of this paragraph a list will be given of the parameters available to the user for checking program speed and accuracy al Limits for accuracy check in calculation of flux amplitude EPS1 and EPS2 in block KINPUT Recommen dations as to their values are given in the input list based on the results of very stringent accuracy tests Larger values are feasible but will not result in appreciable time savings since the point kinetics module is the least time consuming module of all 24 bi Maximum error of reacticity neutron lifetime and effective delayed neutron fraction at end of normal interval EPS4 in block KINPUT The number of inner iterations and the accuracy of temperatures and feed back material motions are determined by this limit c1 Limits for alterations of zone dependent contributions to point kinetics coefficients EPS5 in block KINPUT These limits determine the frequency of shape func tion recalculations Recommendations as to their values are included in the input description c2 Maximum error of reactivity at end macro interval
71. on by another This kind of perturbation may be used to simulated control rod movement b2 Replacing one macro material i e fuel coolant cladding etc by another or by vacuum With this kind of perturbation voiding or fuel coolant inter action without fuel movement may be simulated 15 b3 Moving a macro material from one zone into another This kind of perturbation can be used to simulate slumping or fuel movement An important limitation to the simulation of external perturbations is that no thermodynamics data of a zone are changed as a result of an external perturbation affecting that zone This should be kept in mind when defining external perturbations for zones pertaining to the thermodynamics geometry if the old thermodynamics modules are used For the new thermodynamics modules use of perturbation types bi b3 in thermodynamics zones is forbidden 2 7 Time Step automatization and iterative procedure The processes described by KINTIC have widely varying time scales with on the one hand the extremely fast development of the neutron population which is charac terized by the fast neutron lifetime of a few 1077 Seconds On the other side of the spectrum the changes of the shape function or for the loss of flow case the changes of material temperatures at the beginning of the transient have time scales of the order of seconds Even the thermo dynamics processes alone exhibit widely varying time scales with sudde
72. oolant velocities and phase transitions Thus no treatment of flow coast down and of all material movements initiated by a transient boiling slumping FCI is possible Simulation of mat erial movements is possible by treating them as external perturbations but in this case the changes of thermody namics conditions e g reduced heat transfer to coolant due to boiling are not accounted for In 1975 76 KINTIC 2 was coupled to the thermodynamics mo dules contained in CAPRI 2 5 The resulting code system is now able to treat the following effects occuring in a transient Steady state and transient heat conduction and heat transfer steady state and transient pressure distrib ution along the coolant channel including flow coast down 10 fuel pin deformation and cladding failure fuel coolant interaction sodium boiling cladding and fuel relocation slumping This system of modules may be augmented by newer modules especially by a module for cladding move ment and relocation for the time before onset of fuel slumping In all modules a single channel model is used with up to 30 channels on different radial positions representing the original three dimensional configuration It is left to the user to decide which subassemblies are sufficiently similar with respect to position burnup power production and power coolant flow ratio to be represented by one channel One coolant channel contains fuel pellet cladding and a
73. ovided in this special case 4 Geometrical representation of the reactor 4 1 Introduction The geometrical description of the reactor especially for cases employing the new thermodynamics has become much more complicated than the one used in 1 In the old code the zones employed for calculation of neutronics feedback and thermodynamics are basically the same with the only peculiarity that a difference is made between feedback and non feedback zones the latter comprising e g reflectors or absorbers Two factors mainly com plicated this simple picture a The new scheme for treating group constants described in 1 This concept had to be adapted since the scheme used in KINTIC 1 one set of group constants per feedback zone containing all information on temperature and composition dependence proved too cumbersome for large cases In the new scheme the reactor is divided up into subzones for the calculation of group constants each subzone encompassing several feedback or non feedback zones as a rule Microscopic group constants are constant in each subzone but may de pend on temperature and composition thus the infor mation on temperature and composition dependence is to be stored once for every subzone The actual macro 27 scopic group constants for each feedback zone 1 culated from this information using the actual tempera tures and compositions and thus result in one set of group const
74. proportional share of coolant and structure material Axial distributions are represented by axially subdividing the channel including fission gas plenum and mixing cham ber into up to 30 zones In the steady state and transient one phase thermohydraulics modules heat conduction is radial in fuel pellet and cladding whereas heat conduction in the coolant and axial heat conduction in fuel and cladding are neglected A central hole in the pellet and a gap between pellet and cladding are accounted for Heat is removed from the cool ant channel by the axial motion of the coolant this is governed by the pressure drop between coolant inlet and outlet which may be time dependent In addition to the temperature fields time dependent densities volume fractions and axial expansions are calculated for further use in the feedback routines In part these numbers are derived from the results produced by the modules described hereafter Pin deformation and failure are calculated using the BREDA model 9 which includes burnup effects This model takes into account steady state swelling production and partial release of fission gas and radial porosity distrib adio ution with fuel restructuring transient fission gas release fuel swelling and changing material properties of the cladding For the calculation the pin is axially subdivided into mechanically uncoupled cylinder segments and a model based on an axisymmetric quasistatic plane s
75. r units of typically 1000 2000 MWe power accident analysis employing multidimensional neutronics are gaining in importance at least as a means of checking or adjusting simpler calcula tional tools The development of multidimensional dynamics codes for fast reactors has started long ago In GfK the two dimensional dynamics code for the predisassembly phase KINTIC 1 was developed and documented in 1972 4 This code while an important first step and a good basis for further development was lacking in a number of respects and needed improvement Apart from a big number of minor alterations the following important improvements were realized and incorporated into KINTIC 2 in the meantime 1 For calculating time dependent neutronics KINTIC 1 pro vided the point kinetics adiabatic and normal quasi static method The improved quasistatic method was in corporated additionally in the new version 2 The organization of group constants was basically al tered The need for doing so was already anticipated in 4 due to the fact that the old concept resulted in too big a number of data to be shuffled and calculated Instead of correlating the basic data with the single feedback zone as was done in the old code basic data are now correlated with so called reactor subzones e g core zone radial blanket or absorber Apart from a dif ferent organization and smaller blocks of data the con cept now allows to take into account composition depe
76. together with the rules linking it to the other meshes A special section is devoted to the representation of control rods In any case the user is strongly advised to make a Sketch of the geometry for even a simple problem con taining all infoxmation on the different meshes This greatly helps with the production of the input even in the case in which the old thermodynamics and therefore the simpler mesh is used 4 2 Geometry for group constants The contents of this section is a repetition from 1 but will be given here for completion of the geometrical picture Since a discussion of geometrical representations remains too abstract without pictures a configuration typical for a small fast reactor is used for demonstration Fig 4 shows this reactor containing core and blanket zones absorber follower reflector and coolant and fission gas plenum The figures used in this and the following three sections for describing the different meshes always pertain to the basic geometry shown in fig 4 Fig 5 shows the subzone configuration of the reactor 10 subzones are used for describing the different micro scopic group constants taking into account differences in Steady state material composition and in collapsing Spectrum The latter criterium is applied but once in the radial blanket which is subdivided into an inner and an outer zone with a harder and a softer collapsing spectrum 29 It should be noted in fig 5 that the
77. train approximation is used The results of BREDA i e dimensions of the central hole width of gap between fuel and cladding radial and axial expansion fuel melt frac tion and plastic deformation of cladding are feedback to the other modules for use in the calculation of the temperature fields feedback and the initiation of fuel coolant interaction or slumping Fuel coolant interaction is initiated when the fraction of molten fuel and either the mean cladding temperature or the plastic deformation of the cladding exceed user specified limits in a specified number of axial nodes The interaction is calculated with a model similar to the Cho Wright model 11 but with a more refined treatment of heat transfer from fuel to sodium in the two phase region following the model of Caldarola 6 Only a specified fraction of the molten fuel in the cavity at time of failure participates in the reaction Fuel ejection fission heating chilling axial motion and condensation are neglected Sodium voiding is calculated with BLOW 3 7 a code using a multiple bubble slug ejection model which has been checked by experiments Boiling is initiated when the maximum coolant temperature exceeds the sodium boiling temperature plus a user specified channel dependent superheat Space dependent vapour pressure inside the bubble and evaporation and condensation of a liquid sodium film including sub assembly wall effects are taken into account 2128
78. ubzones if any assignment of variants of subzones to DIXY zones INSTIT Control data for stationary critically search option provided by KINTIC 2 36 FEEDBC Old or no thermodynamics Thermodynamics con trol data and input CAPRI 2 thermodynamics Assignment of thermo dynamics channels and axial zones to feedback channels and axial zones THEIN Control data and thermodynamics input for CAPRI thermodynamics The geometry for DIXY and the control data for the two dimensional calculation of the shape function are con tained in the remaining two blocks DX LDIM and DXDIF DXBUCK contains the bucklings if any The notation used on the following pages is Knn for the Start of a sequence of input data Snn for a logical decision or involving a skipping of data All input is unformatted and governed by the rules for KAPROS input 121 A final remark must be made with regard to the input description contained in this report This is the des cription as of the beginning of 1977 It may be subject to changes since all modules may be further refined and new modules requiring additional input e g one for cladding motion may be added The newest input des cription may be obtained by starting a KINTIC job with the input block KINPUT containing the constant DESCR see the following description of KINPUT 597 6 1 BLOCK KINPUT KAPROS CONTROL CARD KSTOX CBN KINPUT f TYP CARD P M KINPRM IF ANY ONE THE BLOCKS FEEDBC
79. wer distribution and source distribution of delayed neutrons IN R processing of neutronics input KEFFIT Stationary consistency iteration and criticality search QSUM calculation of group constants Old thermodynamics INSTEM instationary one phase thermodynamics STATEM stationary thermodynamics Coupling of neutronics and new thermodynamics BL TH initialization of thermodynamics data before start of instationary calculation THINIT processing of thermodynamics input CAPRI 2 thermohydraulics and material motion BREDA pin deformation and failure CLADM dummy module FCIKU fuel coolant interaction FSLUM slumping of fuel and cladding ITCB sodium voiding ITC1 one phase instationary thermohydraulics STATO stationary thermohydraulics 23 5 1 controlling module for instationary thermodynamics and material motion f DIXY system 13 for diffusion calculations DIXIN processing of input for DIXY DXDIFF calculation of shape function g Auxiliary INDES output of input description The number of data blocks is at the moment up to 44 depending on the case to be calculated and excluding the up to 7 input blocks which are the only ones to be pro vided by the user 14 of the 44 data blocks are manifold with 2 3 or 4 versions depending on the type of block Another 3 data blocks exist in as many versions as there are thermodynamics channels in the case to be calculated only for the CAPRI 2 thermodynamics being used i e
80. ynamics four iterations are used Apart from these calculations the steady state part of KINTIC 2 see fig 1 comprises the determination of the steady state adjoint and in preparation for the instation ary calculations an estimate of the initial reactivity ramp as given by the external perturbation see 2 6 2 3 Neutron kinetics The instationary neutronics calculations may be performed with a number of approximate methods These are a the normal or improved quasistatic method b the adiabatic method c a primitive point kinetics method which does not use reactivity coefficients provided by input but only first order perturbation theory with normal and adjoint flux pertaining to steady state conditions 6 A detailed derivation of the quasistatic method was given in 4 and may be found elsewhere in literature 10 Here only the main formulas will be listed The time dependent equations for neutron flux and precursor densities are written as X 30 x 09 xt 2 1 t time v neutron velocity neutron flux S operator for removal diffusion and scattering yP prompt neutron spectrum MP prompt fission yield x2 aelayed neutron spec trum of precursor i A decay constant of precursor i C7 concentration of precursor i dag M d 2 9 i Cy Mj precursor fission yield of precursor i and the equation for the steady state adjoint P a we 5 Jj x ME x

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