ENTRY 22998 20080320 21972299800000001 SUBENT 22998001 20080320 21972299800100001 BIB 18 98 2299800100002 TITLE .Thermal-Neutron Capture Cross Section and Resonance 2299800100003 Integral of Americium-241 2299800100004 AUTHOR (Shoji NAKAMURA, Masayuki OHTA, Hideo HARADA, 2299800100005 Toshiyuki FUJII, Hajimu YAMANA) 2299800100006 INSTITUTE (2JPNJAE) Japan Atomic Energy Agency, 2-4 Shirane, 2299800100007 Shirakata, Tokai-mura, Naka-gun, Ibaraki-ken. 2299800100008 Nakamura,Corresponding author, E-mail: nakamura.shoji 2299800100009 @jaea.go.jp; Ohta, Harada. 2299800100010 (2JPNKTO) Research Reactor Institute, Kyoto University,2299800100011 2-1010 Asashiro Nishi, Kumatori-cho, Sennan-gun, 2299800100012 Osaka. Fijii, Yamana. 2299800100013 REFERENCE (J,NST,44,(12),1500,200712) Main reference, data given 2299800100014 (J,NST,40,559,2003) Neutron spectrum determination 2299800100015 (J,NST,43,1441,2006) Neutron spectrum determination 2299800100016 REL-REF (R,,R.B.FIRESTONE+,B,FIRESTONE,,1995) Decay constants 2299800100017 (R,,S.F.MUGHABGHAB+,B,NEUT.CS 1A,,1981) Nuclear data 2299800100018 (R,,S.F.MUGHABGHAB+,B,NEUT.CS 1B,,1981) used for the 2299800100019 (R,,S.F.MUGHABGHAB+,B,NEUT.CS 2,,1981) cross sections 2299800100020 (R,,S.F.MUGHABGHAB+,R,INDC(NDS)-440,2003) determination2299800100021 FACILITY (REAC,2JPNKTO) Kyoto University Research Reactor 2299800100022 INC-SOURCE (REAC) Long-irradiation plug of the Kyoto University 2299800100023 Research Reactor, KUR 2299800100024 INC-SPECT .Maxwell spectrum for thermal neutrons with epithermal 2299800100025 neutron admission. Cut-off energy was obtained with 2299800100026 the help of Gadolinium neutron filter. 2299800100027 METHOD (ACTIV) Activation 2299800100028 (ASPEC) Alpha spectroscopy 2299800100029 (SITA) Single target sample-monitor irradiation 2299800100030 (FNB) Filtered neutron beam used with Gadolinium 2299800100031 foil as a filter. Measurements made with and without 2299800100032 this filter. 2299800100033 PART-DET (G,A) Gamma rays from irradiated monitor wires and 2299800100034 alpha particles from irradiated Am-241 samples 2299800100035 DETECTOR (SIBAR) Silicon surface-barrier alpha spectrometer 2299800100036 (HPGE) High purity Germanium detector with relative 2299800100037 efficiency 25% to 7.6 cm long times 7.6 cm diameter 2299800100038 Na-I(TL) detector, energy resolution 1.9 keV at 2299800100039 1.33 MeV gamma peak of Co-60. 2299800100040 ANALYSIS (DECAY) 2299800100041 DECAY-DATA (95-AM-241,432.2YR,A,5486.,0.845, 2299800100042 A,5443.,0.130) 2299800100043 (95-AM-242-M,141.YR,DG,,0.99541) 2299800100044 (95-AM-242-G,16.02HR,B-,,0.827) 2299800100045 (95-AM-243,7370.YR,A,5275.,0.874, 2299800100046 A,5233.,0.110) 2299800100047 (96-CM-242,162.8D,A,6113.,0.740, 2299800100048 A,6069.,0.250) 2299800100049 (94-PU-238,87.7YR,A,5499.,0.7091, 2299800100050 A,5456.,0.2898) 2299800100051 SAMPLE .Americium sample was Am-241 standardized solution 2299800100052 (0.5 mol/L(M)H-Cl), contained 0.064% Am-243 impurity. 2299800100053 Two samples of 100 Bq (2.5 milliliter solution) and 2299800100054 500 Bq (12.5 milliliter solution) were prepared. 2299800100055 Solutions were dropped in quartz tubes, dried and 2299800100056 sealed. Than placed in two aluminium cases one into 2299800100057 another, two such cases. One of them wrapped in a 2299800100058 gadolinium band. 2299800100059 .For monitors were used wires of Co/Al alloy (Co:0.46 2299800100060 +-0.1wt%, 0.381 mm in diameter) and Au/Al alloy 2299800100061 (Au: 0.112+-0.01 wt%, 0.510 mm in diameter). For 2299800100062 irradiation with Gadolinium Co/Al alloy mass is 2299800100063 0.5991 mg, Au/Al mass is 0.6599 mg. For irradiation 2299800100064 without Gadolinium Co/Al alloy mass is 0.3863 mg, 2299800100065 Au/Al mass is 0.3346 mg. 2299800100066 .Since 59Co and 197Au have different sensitivities to 2299800100067 thermal and epithermal neutrons, those wires are 2299800100068 appropriate for determining the thermal and epithermal2299800100069 fractions in the neutron flux. 2299800100070 ASSUMED (ASSUM1,95-AM-241(N,G)95-AM-242-M,,SIG) 2299800100071 (ASSUM2,95-AM-241(N,G)95-AM-242-G,,SIG) 2299800100072 (ASSUM3,95-AM-241(N,F),,SIG) 2299800100073 MISC-COL (MISC1) <95-AM-242-M(N,G)95-AM-243,,SIG> 2299800100074 (MISC2) <95-AM-242-M(N,F),,SIG> 2299800100075 (MISC3) <95-AM-242-G(N,G)95-AM-243,,SIG> 2299800100076 (MISC4) <96-CM-242(N,G)96-CM-243,,SIG> 2299800100077 (MISC5) <96-CM-242(N,F),,SIG) Maximal value 2299800100078 (MISC6) <95-AM-243(N,G)95-AM-244,,SIG> 2299800100079 (MISC7) <95-AM-241(N,G)95-AM-242-M,,RI) 2299800100080 (MISC8) <95-AM-241(N,G)95-AM-242-G,,RI) 2299800100081 (MISC9) <95-AM-241(N,F),,RI) 2299800100082 <95-AM-242-M(N,F),,RI> = 1800+-65 barn 2299800100083 <96-CM-242(N,G)96-CM-243,,RI>=110+-20 barn 2299800100084 <95-AM-243(N,G)95-AM-244,,RI>=1820+-70 barn 2299800100085 ERR-ANALYS (ERR-T) Total errors of measurements are given 2299800100086 (ERR-S) Statistical error of alpha-ray measurements 2299800100087 (ERR-SYS) Systematic error equal to square root of the 2299800100088 quadratic sum of ERR-1 to ERR-7 errors given below 2299800100089 (ERR-1) Am-241 half-life error 2299800100090 (ERR-2) Am-241 cross sections SIGMA-g, SIGMA-f error 2299800100091 (ERR-3) Am-242-g cross section SIGMA-g error 2299800100092 (ERR-4) Am-242-g branching ratio error 2299800100093 (ERR-5) Cm-244 half-life error 2299800100094 (ERR-6) Irradiation time error 2299800100095 (ERR-7) Cooling time error 2299800100096 .Other errors presented in Table 6 of main reference 2299800100097 are negligible 2299800100098 (ERR-9) Error of the 9th miscellaneous value 2299800100099 HISTORY (20080320C) SM 2299800100100 ENDBIB 98 0 2299800100101 COMMON 17 9 2299800100102 ERR-S ERR-SYS ERR-1 ERR-2 ERR-3 ERR-4 2299800100103 ERR-5 ERR-6 ERR-7 ASSUM1 ASSUM1-ERR ASSUM2 2299800100104 ASSUM2-ERR ASSUM3 ASSUM3-ERR MISC1 MISC1-ERR 2299800100105 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2299800100106 PER-CENT PER-CENT PER-CENT B B B 2299800100107 B B B B B 2299800100108 1. 0.45 0.16 0.13 0.05 0.36 2299800100109 0.1 0.12 0.003 54. 5. 533. 2299800100110 13. 3.20 0.09 2000. 600. 2299800100111 ENDCOMMON 9 0 2299800100112 ENDSUBENT 111 0 2299800199999 SUBENT 22998002 20080320 21972299800200001 BIB 4 9 2299800200002 REACTION (95-AM-241(N,G)95-AM-242-G,,SIG) Cross section at 2299800200003 neutron velocity 2200 m/sec 2299800200004 MONITOR ((MONIT1)27-CO-59(N,G)27-CO-60,,SIG) 2299800200005 ((MONIT2)79-AU-197(N,G)79-AU-198,,SIG) 2299800200006 DECAY-MON (27-CO-60-G,5.2714YR,DG,1173.,0.999736, 2299800200007 DG,1333.,0.999856) 2299800200008 (79-AU-198-G,2.69517D,DG,412.,0.9558) 2299800200009 ASSUMED (ASSUM4,27-CO-59(N,G)27-CO-60,,RI) 2299800200010 (ASSUM5,79-AU-197(N,G)79-AU-198,,RI) 2299800200011 ENDBIB 9 0 2299800200012 COMMON 17 9 2299800200013 MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR ASSUM4 ASSUM4-ERR 2299800200014 ASSUM5 ASSUM5-ERR MISC2 MISC2-ERR MISC3 MISC3-ERR 2299800200015 MISC4 MISC4-ERR MISC5 MISC6 MISC6-ERR 2299800200016 B B B B B B 2299800200017 B B B B B B 2299800200018 B B B B B 2299800200019 37.18 0.06 98.65 0.09 75.9 2.0 2299800200020 1550. 28. 6950. 280. 2100. 200. 2299800200021 16. 5. 5. 75.1 1.8 2299800200022 ENDCOMMON 9 0 2299800200023 DATA 9 1 2299800200024 EN DATA ERR-T MISC7 MISC7-ERR MISC8 2299800200025 MISC8-ERR MISC9 ERR-9 2299800200026 EV B B B B B 2299800200027 B B B 2299800200028 0.0253 628. 22. 195. 20. 1230. 2299800200029 100. 14.4 1.0 2299800200030 ENDDATA 6 0 2299800200031 ENDSUBENT 30 0 2299800299999 SUBENT 22998003 20080320 21972299800300001 BIB 4 9 2299800300002 REACTION (95-AM-241(N,G)95-AM-242-G,,RI) Full resonance 2299800300003 integral 2299800300004 MONITOR ((MONIT3)27-CO-59(N,G)27-CO-60,,RI) 2299800300005 ((MONIT4)79-AU-197(N,G)79-AU-198,,RI) 2299800300006 DECAY-MON (27-CO-60-G,5.2714YR,DG,1173.,0.999736, 2299800300007 DG,1333.,0.999856) 2299800300008 (79-AU-198-G,2.69517D,DG,412.,0.9558) 2299800300009 ASSUMED (ASSUM4,27-CO-59(N,G)27-CO-60,,SIG) 2299800300010 (ASSUM5,79-AU-197(N,G)79-AU-198,,SIG) 2299800300011 ENDBIB 9 0 2299800300012 COMMON 17 9 2299800300013 MONIT3 MONIT3-ERR MONIT4 MONIT4-ERR ASSUM4 ASSUM4-ERR 2299800300014 ASSUM5 ASSUM5-ERR MISC2 MISC2-ERR MISC3 MISC3-ERR 2299800300015 MISC4 MISC4-ERR MISC5 MISC6 MISC6-ERR 2299800300016 B B B B B B 2299800300017 B B B B B B 2299800300018 B B B B B 2299800300019 75.9 2.0 1550. 28. 37.18 0.06 2299800300020 98.65 0.09 6950. 280. 2100. 200. 2299800300021 16. 5. 5. 75.1 1.8 2299800300022 ENDCOMMON 9 0 2299800300023 DATA 9 1 2299800300024 EN-MIN DATA ERR-T MISC7 MISC7-ERR MISC8 2299800300025 MISC8-ERR MISC9 ERR-9 2299800300026 EV B B B B B 2299800300027 B B B 2299800300028 0.107 3.5 E+03 3. E+02 195. 20. 1230. 2299800300029 100. 14.4 1.0 2299800300030 ENDDATA 6 0 2299800300031 ENDSUBENT 30 0 2299800399999 ENDENTRY 3 0 2299899999999