ENTRY 23002 20220216 23102300200000001 SUBENT 23002001 20220216 23102300200100001 BIB 17 58 2300200100002 TITLE New measurement of the 12C(n,gamma)13C reaction cross 2300200100003 section 2300200100004 AUTHOR (T.Ohsaki, Y.Nagai, M.Igashira, T.Shima, K.Takeda, 2300200100005 S.Seino, T.Irie) 2300200100006 INSTITUTE (2JPNTIT) Department of Applied Physics 2300200100007 (2JPNTIT) Research Laboratory for Nuclear Reactors 2300200100008 REFERENCE (J,AJ,422,912,199402) Main reference 2300200100009 ((S,ISINN-2,184,1994)=(R,JINR-E3-94-419,184,1994)) 2300200100010 Same as AJ,422. Graphs and formulas are given 2300200100011 ((S,JAERI-C-97-004,131,1997)= 2300200100012 (S,INDC(JPN)-178,47,1997)) - Same data given 2300200100013 REL-REF (R,,M.A.Lone,C,81GRENOB,,383,1981) Branching ratios 2300200100014 of cascade gamma at thermal neutron energy 2300200100015 FACILITY (VDGT,2JPNTIT) The 3.2 MV PELLETRON accelerator of the 2300200100016 Research Laboratory for Nuclear Reactors at the Tokyo 2300200100017 Institute of Technology. 2300200100018 MONITOR (79-AU-197(N,G)79-AU-198,,SIG) 2300200100019 MONIT-REF (,R.L.Macklin+,J,PR,159,1007,1967) 2300200100020 197Au(n,g)198Au cross section (ENDF/B-V) 2300200100021 PART-DET (N,G) 2300200100022 INC-SOURCE (P-LI7) 7Li(p,n)7Be at 1.895 and 1.995 MeV 2300200100023 SAMPLE - Target is natural. 2300200100024 - Chemical-form of target is element. 2300200100025 - Physical-form of target is solid. 2300200100026 - Target-thickness: 60.2 mm (diameter) and 24.8 mm 2300200100027 (thickness) 2300200100028 METHOD (TOF) To determine incident neutron energy spectrum 2300200100029 DETECTOR (NAICR) Anti-Compton NaI(TL) scintillation detector 2300200100030 for prompt gamma ray detection. Consists of 7.6 cm 2300200100031 diameter, 15.2 cm long NaI(Tl) detector surrounded 2300200100032 by annular 25.4 cm diam. * 28.0 cm ling anti-Compton 2300200100033 detector 2300200100034 (GLASD) Li-6 scintillation glass detector for neutron 2300200100035 spectrum measurement 2300200100036 CORRECTION .Corrections were made for multiple scattering and 2300200100037 capture of neutrons in gold monitor and sample. 2300200100038 Corrections obtained by Monte-Carlo method 2300200100039 ADD-RES .Analytic form of Maxwellian averaged cross section and2300200100040 .Data capture cross section obtained by the fit of the 2300200100041 partial cross sections represented by the formula (3) 2300200100042 given in the text, page 187. of ISINN-2,1994 : 2300200100043 ! Sigma(E) = (17.0+-0.3)/sqrt(E) + (1.50+-0.11)*sqrt(E)2300200100044 where E is the center-of-mass energy 2300200100045 .Data for MACS obtained from the fit of the total 2300200100046 capture cross sections and represented by the formula 2300200100047 (6) given in the text, page 188. of ISINN-2,1994 : 2300200100048 ! = (17.0+-0.3) + (2.25+-0.17)*KT)*/sqrt(KT)2300200100049 STATUS (APRVD) Proofread by Toshiro Ohsaki (2007.11.19) 2300200100050 HISTORY (20070929C) 2300200100051 (20081103U) MONITOR keyword added - SM 2300200100052 (20091015U) Analytic forms of cross sections added. 2300200100053 FACILITY code (VDG to VDGT) corrected. 2300200100054 Reference ISINN-2,184 added - SM 2300200100055 (20130203A) SD: Ref. on JAERI added. E-LVL changed on 2300200100056 LVL-NUMB (no information about values in the article) 2300200100057 in Subent 002. 2300200100058 (20220216U) SD: Year of the JAERI-C-97-004,131 ref. 2300200100059 updated (1996 -> 1997). 2300200100060 ENDBIB 58 0 2300200100061 NOCOMMON 0 0 2300200100062 ENDSUBENT 61 0 2300200199999 SUBENT 23002002 20130203 22342300200200001 BIB 5 7 2300200200002 REACTION (6-C-12(N,G)6-C-13,PAR,SIG) 2300200200003 EN-SEC (LVL-NUMB,6-C-13) 2300200200004 ERR-ANALYS (DATA-ERR) No information on source of uncertainties 2300200200005 STATUS (TABLE) Taken from Table 2, p.914 of AJ,422 2300200200006 HISTORY (20091015U) E-LVL-FIN changed to E-LVL 2300200200007 (20130203A) SD: E-LVL changed on LVL-NUMB (no 2300200200008 information about values in the article) 2300200200009 ENDBIB 7 0 2300200200010 NOCOMMON 0 0 2300200200011 DATA 6 24 2300200200012 EN-MEAN +EN-RSL -EN-RSL LVL-NUMB DATA DATA-ERR 2300200200013 KEV KEV KEV NO-DIM MICRO-B MICRO-B 2300200200014 21. 5. 9. 0. 3.0 0.8 2300200200015 21. 5. 9. 1. 6.7 1.2 2300200200016 21. 5. 9. 2. 1.3 1.3 2300200200017 21. 5. 9. 3. 0.9 0.9 2300200200018 40. 10. 10. 0. 1.2 0.4 2300200200019 40. 10. 10. 1. 8.7 1.0 2300200200020 40. 10. 10. 2. 0.9 1.2 2300200200021 40. 10. 10. 3. 0.4 0.5 2300200200022 50. 20. 20. 0. 1.8 0.6 2300200200023 50. 20. 20. 1. 8.6 1.1 2300200200024 50. 20. 20. 2. 1.0 0.5 2300200200025 50. 20. 20. 3. 1.9 0.9 2300200200026 60. 15. 30. 0. 2.2 0.7 2300200200027 60. 15. 30. 1. 11.2 1.5 2300200200028 60. 15. 30. 2. 1.1 1.0 2300200200029 60. 15. 30. 3. 1.5 2.8 2300200200030 97. 33. 27. 0. 1.0 0.3 2300200200031 97. 33. 27. 1. 12.3 1.3 2300200200032 97. 33. 27. 2. 0.6 0.4 2300200200033 97. 33. 27. 3. 1.3 1.0 2300200200034 199. 51. 39. 0. 1.6 0.7 2300200200035 199. 51. 39. 1. 16.5 2.2 2300200200036 199. 51. 39. 2. 0.7 0.7 2300200200037 199. 51. 39. 3. 2.8 3.4 2300200200038 ENDDATA 26 0 2300200200039 ENDSUBENT 38 0 2300200299999 SUBENT 23002003 20071203 21892300200300001 BIB 3 4 2300200300002 REACTION (6-C-12(N,G)6-C-13,,SIG) 2300200300003 ERR-ANALYS (DATA-ERR) No information on source of uncertainties 2300200300004 STATUS (TABLE) Taken from Table 2, p914 of reference 2300200300005 (DEP,23002002) Partial cross section 2300200300006 ENDBIB 4 0 2300200300007 NOCOMMON 0 0 2300200300008 DATA 5 6 2300200300009 EN-MEAN +EN-RSL -EN-RSL DATA DATA-ERR 2300200300010 KEV KEV KEV MICRO-B MICRO-B 2300200300011 21. 5. 9. 11.9 2.2 2300200300012 40. 10. 10. 11.2 1.7 2300200300013 50. 20. 20. 13.1 1.6 2300200300014 60. 15. 30. 15.9 3.4 2300200300015 97. 33. 27. 15.2 1.7 2300200300016 199. 51. 39. 21.6 4.1 2300200300017 ENDDATA 8 0 2300200300018 ENDSUBENT 17 0 2300200399999 SUBENT 23002004 20071203 21892300200400001 BIB 3 4 2300200400002 REACTION (6-C-12(N,G)6-C-13,,SIG,,MXW,DERIV) 2300200400003 ERR-ANALYS (DATA-ERR) No information on source of uncertainties 2300200400004 STATUS (TABLE) Taken from text, p915 of reference 2300200400005 (DEP,23002003) Energy dependent neutron cross section 2300200400006 ENDBIB 4 0 2300200400007 NOCOMMON 0 0 2300200400008 DATA 3 1 2300200400009 KT DATA DATA-ERR 2300200400010 KEV MICRO-B MICRO-B 2300200400011 30. 15.4 1.0 2300200400012 ENDDATA 3 0 2300200400013 ENDSUBENT 12 0 2300200499999 ENDENTRY 4 0 2300299999999