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JNC-TN9410-2001-015:1.43MB

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2. JNC TN9410 2001 015 July 2001 Simulation of REM Counter s Response and Accommodation to the Revised Fluence Dose Conversion Coefficients Makoto Hashimoto Kei Saito International Commission on Radiological Protection ICRP recommended the revision of the exposure dose evaluation system in 1990 Recommendation of the ICRP Adopted by the Commission on Nov 1990 Publication 60 On the basis of this recommendation J apan revised the regulations about dose evaluation system and took effect them
3. MORO OM ES BS CMH SHERDASITISIHSED SHAMS HEL 1 TCRP Publication 74 Conversion Coefficients for use in Radiological Protection against External Radiation Pub 74 7
4. Studsvik 2202D BF 2 Pub 219 0 1 4 22020 JNC TN9410 2001
5. Pub 515 lem AP Pub 743 AP 4 JNC TN9410 2001 015 3 3 1 Studsvik 2202D 9 1 MCNP 4B9
6. Pub 21 0 36 cps Sv h Pub 74 0 42 cps Sv h 2222D Pub 51 0 44 cps u Sv h Pub 51 570 1000 OTF6NIL ONT JNC TN9410 2001 015 2 21 2202D Am Be 2 2 gt lt
7. 7 Pub 60 13 4 1 2 ICRP ICRP Publication21 Data for Protection against Ionizing Radiation from External Sources supplement to ICRP Publication 18019 Pub 21 ICRP Publication51 Data for Use in Protection Against External Radiation i 5 51 Pub 74 1985
8. 10 RI 1MeV 4 7 Am Be Am Be
9. np 8 4 Neutron Sensitivity cps per flux Eli 1 x 1 0E 01 ie Att 1 o T Heo ime 5 ll HE Hin 1111 11M HU x Ht HT Im III sun mim as 4 Hill A 1 E 08 1 E 07 1 06 1 05 1 04 1 03 1 02 1 01 1 E 00 T E 01 1 E 02 Neutron Energy MeV 3 3 2202D 1 910 1000 OTP6NL ONL Neutron Sensitivity cps per flux ae ili I IH
10. Pub 51x2 Pub 51 2 Pub 74 Pub 74 Pub 21 21 INC TN9410 2001 015 pSv om 102 109 10 Pub 51 AP Pub 512 Pub 74 AP gt amp Pub 21 10 107 10 10 10 10 MeV 1 2 Pub 51 Pub 51 AP ULH Pub 51x2 Pub 51 API 2 Pub 74 AP Pub 74 AP
11. 21 5 30 6 30 30 JNC TN9410 2001 015 gt lt 11 1cm 12 18 1 4 2202D 2 1 341 2202D 92 MCNF4 3 3 2202D 1 84 2202D 85 2202D 3 41 Am B 42 Am Be 48 252Cf 44 252Cf 4 5 4 6 4 7 8 1 4 81 4 1 ICRP Pub 51
12. NRESP9 MCNP 4B _ 3 1 3 1 3 4 3 2 O 10 95 400mmHg
13. 3 75X102 8wjh cpml Pub 515 lem 0 5913 eps flux Am Be 4 2 3 4 0 411 cps fuxl _ 780mmHg 3 5 2202D 00 2 21 Am Be N 2 301 x10 n s 1982 8 9 433y
14. MCNP 4B89 2 8 508mmHg 3 3 1eV 4MeV A
15. 10B 1B 19 8 80 2 BED SHE JNG TN9410 2001 015 STUDSVIK INSTRUNENT AS dud UNT ELECTRON BATT 1 22202 SS 1 1 1 I l l eS N 297 I i i 1 l H h amp emma 1 lt lt x lt lt z IUM a t az ery o u ee E DIEE METER 2202 3 Detector Unit 3 1 2202D Studsvik Neutron Dose Rate Meter 2202D JNC TN9410 2001 015 2222 55 25 gt Riper 7222 15 3 4 RE S JNC TN9410 2001 015 3 2 MCNP4 JNC TN9410 2001 015 3 2
16. Am Be Pub 519 lem 8 1 6 4 1 Pub 515 Hs AP i Pub 519 lem H 10 iii Pub 749 H 10 iv Pub 749 AP 4 15 55 4 4 4 5 4 5 Sirnulated Readings of 2202D
17. REE cp Sv h F 73 Sv h epm 8 39 10987 10min 1306 10min 968 1 min 371x107 3 75 x 10 im 24 masm emm _ romi iz emm za5Zmn ao smw Zm iacemm 16047 min 870x107 __ ao 3 sZ zaiemn Yetzzmn 870x107 _ 1 1988 9 12 36 5 U Sv h 3 1 610 1006 OTVENE Neutron Sensitivity eps per flux 1 0 01 1 0E 02 1 0E 03 1i REI Eza j E i TESTI rte l q iii FHHHHI T HHI cl __ ill tt Th IE S WN 26 Ni H ail a LLL HH HH HHI H i Ei B See TE H Ill l ill Torii H
18. Pub 743 Studzyik 2202D 1 ICRP Pub 60 1990 2 ICRP Pub 26 1977 3 ICRP Pub 74 Conversion Coefficients for use in Radiological Protection against External Radiation Annals of the ICRP 1996
19. EE 3 194 i rr NESNE mamami 1 108400 102 01 4 5 r 111 Pe te tt tt A YI TT PUT PPA Fp sau pam Miamis lt Co i KkKRERKK lt EKKS lt NU HTIUSIIIIID _I IN HI HIII KIZII Iu KD DD J WE YY Kho H i Ho aaa n m LLL ims HT Hr tant 1 iss 1 GE 17 1 0 16 1 02 15 102514 1 0 13 eV 1 0E 04 1065 1 0E 00 4 6 4 1 Pub 51 He AP Sv cm 1 00E 05 446 12 1 00E 03 3 83 12 2 00E 02 5 87E 12 1
20. Pub 21 Pub 21 1cm Oi E H 10 Pub 74 HE H 10 Pub 51 an 10 107 10 10 10 10 MeV 1 3 10 Pub 51 A 1om B 670 7002 OTP6NL ONP 109 Pub 21 Pub 74 Pub 51 2202 s cps neutron cm p Pr EI A Er py U lt 10 10 10 10 10 10 MeV 1 4 2202D 21 Pab 74 Pub 51 1 1
21. Hs 4 2 ICRPPub 51 1cm H 10 4 8 TCRPPub 74 H 10 4 4 ICRPPub 74 35450 2202D on oO 18 15 16 19 28 28 24 24 25 25 29 12 18 26 26 27 21 28 JNC TN9410 2001 015 1 1 1 ICRP International Commission on Radiological Protection ICRP 1990 ICRP Publication 60 1990 Recommendations of the ICRP Pub 60 ICRP1977 ICRP Publication 26 Recommendations of the ICRP J 2 Pub 26
22. gt lt ORE 7 z 21 JNC TN9410 2001 015 MCNP 4B8 lt 8
23. III B j HII I crurum m m m H Saas 1 DE 01 I 5 585 5 j UI ee irm j EEIT lilii HN 2 Sees ei 5 111 HH II 22 I i HH TH 2 E MIET 1 2 Tc m m oe HH Dinit Meee TT Hi II T 1 HH EE ND NL MMUUU IT T TITI mitt Ii HILL HHL I I iH IO T I aF FEE Sit 1 4 11 MIAN tL TE 1 l 0 LO UH EE
24. 1 0E 01 00 10 01 1 0E 02 155 03 4 2 Am Be JNC TN9410 2001 015 T 0E 08 10607 TTF Sis LL m sz i E j 10 05 I 9 N PE ILTT a 0 0 I E a I ed TEH LLL 110 1 rr f ht a ke t HEI MI MM I 11 1252 1 0E 03 HIT UP bud IL_ T K fei CT iise a 1 0E 02 HIE I HILL I 1111 SS 222 MEE 3 SS SS 10E 01 ee ee ee a a __ IIIFI II 1 ET 0 TEES ss mE HII I C 1 a nsn o onoo
25. HH Til HHT 1 0 08 1 0 07 1 0 06 1 0 05 1 0 04 1 0E 03 1 0E 02 10 01 1 0 00 1 0E 01 1 0E 02 Neutron Energy MeV 13 5 2202D 3 610 1006 OTVONL ONE JNC TN9410 2001 015 4 4 1 6 4 1 4 6 1 241Am B 2 24Am Be 8 3 252Cf 4 252Cf 5 6
26. ten 1 06400 FEF pman 4 i 1255S SEE 2 h nh sg 10 01 SS 1 ILL 52 cS oo 1 106 02 4 3 ee en nee ep eS ie II 335 1 0E 03 coom a m ier taam LLL 1 1054 1905 05 1 0 08 102 07 1 0 08 T J Sey SS Fa 8 waman eee ML HIHTT Hi et 5 586 S w BELLET aba Pte it soe tI HI EH EE ee EE T zz RREO RaR E 1 SSS 8
27. TC I II T El EAE NEI l T T O A a ttt Ht AH tt tt Tt ec t ji THI THI Eli Eli LZ i I l BI DANN BIB WI lll z H EE E H ee Till LTLLHHHE LT ii Bs sa E EL HHH HHT HHI P A Emas mill 1 0 08 1 0 07 1 0 06 1 0 05 1 0 04 1 0E 03 1 0 02 1 0E 01 1 0E 00 1 0 01 1 0E 02 Neutron Energy MeV 3 4 2202D 2 510 1002 OTFONIL ONL JNC TN9410 2001 015 3 3 8 4 3 1 Am Be
28. Am Be Am Be Pub 749 Pub 519 JNC TN9410 2001 015 JNC TN9410 2001 013 19 7 1 08 19605 iw n ise 3 jaam IIII 11 LL I ICEA a m aa aa aa g IN EN 1 0 04 Am B Hill j HILLLIL Miaa E 11 bn uma ommi 11 Q bt Fa kuma pummmamaq THE l 1 1 0E 03 10 02
29. Evaluated Dose Rate 4 1 4 4 4 5 4 5 Hm Pub 51 H 10 Pub 51 1 Pub 51 JNC TN9410 2001 015 10 Pub 74 E Pub 74 1 Pub 74 Am Be 252Cf H 10 Am Be AmB
30. JNC TN9410 2001 015 Pub 51 2 P E 1 1 1 2 Pub 51 Pub 74 1 3 1 cn 1 8 Pub 51 1cm 1 1 cn lcm Pub 74 leV 40keY
31. 4 5 4 7 H 10 1MeV RIRE E 8MeV 2202D Pub 749 IMeV 42 Pub 749
32. 01 260 01 2 Neutron Spectrum Am B 3 66E OO 6 62E 01 1 0 69498 0 95354 0 98979 1 08504 416E 00 5 91E 01 1 073867 0 98622 1 057881 1 11219 Cf Moderated 1 07E OO 251E 01 1 0 559291 091959 1 04467 0 94401 252Cf 2 13E OO 589E 01 1 052708 0 90166 1 043 090867 JOYO 286E 01 1 5OE 01 1 O 5 89E 01 1 _ 0 89294 3 75 x 10 Sv h cpm 1 2 2 21 670 7002 017651 ONE a e Fission eo i Cf Moderated A HE Pub 51 H 10 Pub 74 O E Pub 74 MeV 4 7 510 1000 OTF6NI ONS JNC TN9410 2001 015 5 1CRP Pub 60
33. 10 5 70E 10 6 00 10 4 00E 10 10 2 60E 10 iCRP Pub 74 2 50 f AP v cm __100 08 6 55E 12 5 0OOE 07 1 28E 11 1 0OE 05 1 51E 11 5 00E 05 1 48E 11 1 00E 04 1 46E 11 2 00E 04 1 44E 11 1 00E 03 142 11 2 00E 03 1 44E 11 5 00 03 1 57E 11 1 OOE 02 1 83E 11 1 _L00E O0O0 2 82E 10 4 3 ICRP Pub 74 4 4 ICRP Pub 74 E 200E 02 2 38E 11 3 OOE 02 2 90E 11 5 OOE 02 3 85E f1 1 00E 01 598E 11 1 50E 01 8 02E 11 2 00E 01 9 90E 11 3 00E 01 1 33E 10 5 OOE 01 1 88E 10 7 00E 01 2 31E 10 9 00E 01 2 67E 10 1 20E 00 3 10E 10 2 00E 00 3 83E 10 3 00E 00 4 32E 10 iCRP Pub 74 394 5 2202D 1 Neutron Spectrum __ Eavorage MeV AmB 366E OO 662E 01 1 49E OO 103E OO 142 00 147E OO 1 62 00 IAm Be 416E OO 591E 01 1 33E OO 983E O1 1 31E 00 141E OO 1 48E OO Cf Moderated 1 07E OO 251E 01 584E 01 3 16E 01 519E 01 590E 01 533 01 Joyo 286E 01 1 50E 01 338E 01 1 30E 01 273E 01 3 23
34. 3MeV13MeV 40MeV Pub 60 RI 5 40key 3MeV 1 3 1 1
35. 00E 01 1 98E 11 500E 01 8 70E 11 1 50E 00 2 00E 00 3 80E 10 ICRP Pub 51 4 2 ICRP Pub 51 1cm H 10 H 10 _ Svrcm MeV 920E 12 __100 403 6 20E 12 _ 200E 01 1 26E 10 1 00 00 3 40E 10 1 50E 00 3 62E 10 2 00E 00 3 52E 10 3 00E 00 3 80E 10 4 00E 00 4 09E 10 0 0 0 3 78E 10 3 83E 4 03E 10 4 17E 4 46E 10 1 1 40E 01 5 20E 1 1 70E 01 6 10E 10 2 00E 01 6 50 10 ICRP Pub 51 970 1000 OTDGNL ONE JNC TN9410 2001 015 10 H 10 MeV Sv cm2 100 08 900 12 5 00 07 1 36E 11 1 13 11 5 00E 05 9 90E 12 5 00E 04 8 30E 12 _ 1 00E 03 7 90E 12 2 00E 03 7 70E 12 8 00E 12 1 00E 02 2 37E 1 1 7 00E 02 8 80E 1 1 2 00E 01 3 00E 01 1 70E 10 2 33 10 3 22 10 3 75E 10 4 00E 10 4 16E 10 4 25E 10 4 20E 10 4 12E 10 4 08 10 4 05 10 4 00 10 7 00 01 9 00 01 1 00E 00 1 20 00 2 00 00 3 00E 00 4 00E 00 5 00E 00 6 00E 00 7 00E 00 8 00E 00 9 00E 00 1 00E 01 1 20 01 1 40 01 1 50E 01 1 60E 01 1 80E 01 2 00E 01 3 00E 01 5 00E 01 7 50E 01 1 00E 02 1 25E 02 1 50E 02 1 75E 02 2 01E 02 4 09 10 4 40 10 4 80 10 _5 40
36. 015 10MeV 100keV 10MeV Pub 74 Pub 21 JNC 9410 2001 015 pSv r tcm Pub 51 gt lt 2 PUD 74 Pub 21 10 10 1 0 10 10 107 10 10 10 MeV 1 MEDIO R SEAS 929 5 RS Pub 51 511 ICRU 1cm
37. 1440 HE LI ett r a 11010 tet 1 51138 Mt 4 4 Cf JNC TN9410 2001 015 WHIP P 1 kE ISSN eee T mm li m SG Esa x 1 111 LLL o KP P PPP LLL LLL L MLULI 1 ITT Jill l J JII 1 me aeae sis SSS k HILL es 2 f Eade a ee ss 1 or 1 FS Z an w m w w v n g s lt ee ee ELLLLL LIL j l 13 ll aa
38. 4 ICRP Pub 21 1971 5 ICRP Pub 51 1970 6 1999 7 Neutron Dose Rate Meter 22020 Studsvik 1991 8 J F Briesmeister Bd MCNP A General Monte Carlo N Particle Transport Code Version 4B LA 12625 M 1997 9 NRESP98 PNC TN9410 98 061 1998
39. JNC 9410 2001 015 2001 7 TH LF ey aS 319 1184 4 49 Inquiries about copyright and reproduction should be addressed to Technical Cooperation Section Technology Management Division Japan Nuclear Cycle Development Institute 4 49 Muramatsu Tokai mura Naka gun Ibaraki 319 1184 Japan Japan Nuclear Cycle Development Institute 2001 JNC TN9410 2001 015 2 0 0 1 7 At MR GCRP 1990 EEE Publication 60 2001 4
40. on and after iis 2001 The conversion coefficients for neutron dose evaluation was also revised Neutron dose is popularly measured with a particular instrument called REM Counter However the revision of the conversion coefficients can cause the REM Counter s response inutile So utilizing the technique about the simulation of radiation detector s response the response of REM counter was evaluated and the compatibility to the new dose evaluation system was discussed The response of the REM counter may not cause serious problem in utilization as usual even though it may undervalue the neutron dose a little Additionally this underestimation can be resolved by proper calibration ee Radiation Control Section Health and Safety Division O arai Engineering Center JNC TN9410 2001 015 gt 1 1 11 ICRP 1 1 2 1 13 2 8 31 8 3 2 8 VD S 0 3 1 10 32 14 3 3 0 17 4 m 20 4 1 20 242

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