ENTRY 22064 20230209 231422064 0 1 SUBENT 22064001 20230209 231422064 1 1 BIB 10 23 22064 1 2 TITLE Mass yields of Am-241 thermal-neutron fission 22064 1 3 AUTHOR (H.Nakahara,I.Fujiwara,H.Okamoto,N.Imanishi, 22064 1 4 M.Ishibashi,T.Nishi) 22064 1 5 REFERENCE (J,JIN,33,3239,1971) 22064 1 6 INSTITUTE (2JPNKTO) 22064 1 7 FACILITY (REAC,2JPNKTO) Kyoto University reactor. 22064 1 8 INC-SOURCE (REAC) Graphite thermal column. 22064 1 9 INC-SPECT Thermal neutron spectrum. Thermal neutron flux 22064 1 10 2.0E+10 neutrons/cm2 sec. Cadmium ratio for Au 22064 1 11 was 5000. 22064 1 12 DETECTOR (GELI) A 20 cm3 GeLi detector was used for measuring 22064 1 13 the fission product activities. The detector 22064 1 14 was calibrated by IAEA standard sources of Am-241, 22064 1 15 Co-57, Hg-203, Cs-137, Mn-54, Co-60, Y-88, and by 22064 1 16 Ce-141, Cr-51 and K-42 whose absolute disintegration 22064 1 17 rates were known. 22064 1 18 CORRECTION No details given. 22064 1 19 HISTORY (19871109C) N.O. 22064 1 20 (19880808U) IF. Small corrections 22064 1 21 (19890130U) IF. 22064 1 22 (19900829A) S.W. Flag and monitor clarified in Subent 322064 1 23 (20230209A) SD: Updated to new date formats,lower case.22064 1 24 Corrections in all Subents. Subent 004 added. 22064 1 25 ENDBIB 23 0 22064 1 26 COMMON 1 3 22064 1 27 EN-DUMMY 22064 1 28 EV 22064 1 29 2.5300E-02 22064 1 30 ENDCOMMON 3 0 22064 1 31 ENDSUBENT 30 0 22064 199999 SUBENT 22064002 20230209 231422064 2 1 BIB 9 35 22064 2 2 REACTION (95-AM-241(N,F)ELEM/MASS,CUM,FY,,SPA) 22064 2 3 FLAG (1.) Both the Mo and Tc measurements result in yield 22064 2 4 values for Mo-99, therefore the value is rather 22064 2 5 an averaged value for Mo. 22064 2 6 (2.) Sum of the yields for 2 isomers 22064 2 7 (3.) Normalized to the yield 3.48% for Ce-143. 22064 2 8 DECAY-DATA (42-MO-99,67.HR,DG,140.,.88) 22064 2 9 (43-TC-99-M,6.HR,DG,140.,.913) 22064 2 10 (47-AG-111-G,7.5D,DG,342.,.06) 22064 2 11 (47-AG-113-G,5.3HR,DG,298.,.072) 22064 2 12 (48-CD-115-G,2.3D,DG,523.,.24) 22064 2 13 (48-CD-117-M,3.4HR,DG,1997.,.219) 22064 2 14 (48-CD-117-G,2.4HR,DG,1577.,.163) 22064 2 15 (51-SB-127,3.89D,DG,473.,.246) 22064 2 16 (51-SB-129-G,4.35HR,DG,813.,.62) 22064 2 17 (56-BA-139,83.MIN,DG,166.,.224) 22064 2 18 (56-BA-140,12.8D,DG,537.,.236) 22064 2 19 (58-CE-141,33.D,DG,145.,.50) 22064 2 20 (58-CE-143,33.HR,DG,293.,.426) 22064 2 21 (60-ND-147,11.1D,DG,91.,.287) 22064 2 22 ASSUMED (ASSUM,95-AM-241(N,F),,SIG,,SPA) Cross section taken 22064 2 23 from BNL-325. 22064 2 24 METHOD Absolute measurement of fission yields. 22064 2 25 (CHSEP) Chemical separation and purification. 22064 2 26 SAMPLE Targets were prepared by drying pure Am-241 nitrate 22064 2 27 (1/400 Pu-239) on a 5.16 mg/cm2 Al foil, 22064 2 28 carefully wrapped. Irradiation times 2 - 10 hours. 22064 2 29 A thin Au foil (100 mg/cm2) was used for 22064 2 30 monitoring the neutron flux. 22064 2 31 ERR-ANALYS (DATA-ERR) The given errors include uncertainties 22064 2 32 in the chemical yield determinations, gamma- 22064 2 33 counting and in the neutron flux determinations. 22064 2 34 STATUS (TABLE) Table 1 of J.Inorg.Nucl.Chem.,33(1971)3239 22064 2 35 HISTORY (19880808U) If. Small corrections 22064 2 36 (20230209A) SD: BIB updated. MONITOR -> ASSUMED. 22064 2 37 ENDBIB 35 0 22064 2 38 COMMON 1 3 22064 2 39 ASSUM 22064 2 40 B 22064 2 41 3.13 22064 2 42 ENDCOMMON 3 0 22064 2 43 DATA 6 12 22064 2 44 ELEMENT MASS ISOMER DATA DATA-ERR FLAG 22064 2 45 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 22064 2 46 43. 99. 6.90E+00 2.60E-01 1.22064 2 47 47. 111. 1.19E+00 4.00E-02 22064 2 48 47. 113. 0. 4.87E-01 1.10E-02 22064 2 49 48. 115. 0. 7.50E-02 8.00E-03 22064 2 50 48. 117. 8.60E-03 2.10E-03 2.22064 2 51 51. 127. 6.60E-01 3.00E-02 22064 2 52 51. 129. 1.32E+00 5.00E-02 22064 2 53 56. 139. 8.68E+00 2.70E-01 22064 2 54 56. 140. 5.63E+00 1.10E-01 22064 2 55 58. 141. 6.73E+00 2.22064 2 56 58. 143. 3.48E+00 3.22064 2 57 60. 147. 1.83E+00 2.22064 2 58 ENDDATA 14 0 22064 2 59 ENDSUBENT 58 0 22064 299999 SUBENT 22064003 20230209 231422064 3 1 BIB 9 42 22064 3 2 REACTION (95-AM-241(N,F)ELEM/MASS,CUM,FY,,SPA) 22064 3 3 DECAY-DATA (38-SR-91,9.67HR,DG,750.,.29) 22064 3 4 (38-SR-92,2.7HR,DG,1383.,.90) 22064 3 5 (40-ZR-95,65.D,DG,724.,.49) 22064 3 6 (40-ZR-97,17.HR,DG,658.,.98) 22064 3 7 (41-NB-97-G,72.MIN,DG,658.,.98) 22064 3 8 (44-RU-103,39.5D,DG,498.,.885) 22064 3 9 (44-RU-105,4.43HR,DG,726.,.48) 22064 3 10 (52-TE-132,77.7HR,DG,228.,.94) 22064 3 11 (53-I-131,8.05D,DG,365.,.81) 22064 3 12 (53-I-133-G,20.8HR,DG,530.,.94) 22064 3 13 (53-I-135,6.7HR,DG,1263.,.34) 22064 3 14 (54-XE-135-G,9.2HR,DG,250.,.97) 22064 3 15 (55-CS-138-G,32.2MIN,DG,1436.,.73) 22064 3 16 (58-CE-141,32.5D,DG,145.,.50) 22064 3 17 (58-CE-143,33.HR,DG,293.,.426) 22064 3 18 (60-ND-147,11.1D,DG,91.,.287) 22064 3 19 MONITOR ((MONIT1)95-AM-241(N,F)42-MO-99,CUM,FY,,SPA) used for 22064 3 20 normalization of the light-mass peak, i.E. A = 91 22064 3 21 to 105. 22064 3 22 ((MONIT2)95-AM-241(N,F)56-BA-139,CUM,FY,,SPA) used for 22064 3 23 normalization of the heavy-mass peak, i.e. A = 131 to 22064 3 24 147. 22064 3 25 DECAY-MON (42-MO-99,67.HR,DG,140.,.88) 22064 3 26 (43-TC-99-M,6.HR,DG,140.,.913) 22064 3 27 (56-BA-139,83.MIN,DG,166.,.224) 22064 3 28 METHOD (ACTIV) Determination of relative mass yields by direct22064 3 29 gamma-ray spectrometry of several fission products 22064 3 30 simultaneously. 22064 3 31 SAMPLE Targets were prepared by drying pure (1/400 Pu-239) 22064 3 32 Am-241 nitrate (about 900 ug Am-241 in 6 cm2 area) 22064 3 33 on a 5.16 mg/cm2 Al foil, placed on a 0.3 mm thick 22064 3 34 plastic frame, and with another Al foil used as a 22064 3 35 catcher. Irradiation times were between 2 and 60 hr. 22064 3 36 ERR-ANALYS (DATA-ERR) The errors given are based on errors due to 22064 3 37 gamma-counting and normalization. 22064 3 38 STATUS (TABLE) Table 2 of J.Inorg.Nucl.Chem.,33(1971)3239 22064 3 39 HISTORY (19880808U) IF. Small corrections 22064 3 40 (19890130U) IF. 22064 3 41 (19900829A) S.W. Flag and monitor clarified. Isomeric 22064 3 42 states added in decay-data. 22064 3 43 (20230209U) SD: BIB updated. 22064 3 44 ENDBIB 42 0 22064 3 45 COMMON 4 3 22064 3 46 MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR 22064 3 47 PC/FIS PC/FIS PC/FIS PC/FIS 22064 3 48 6.90 0.26 8.68 0.27 22064 3 49 ENDCOMMON 3 0 22064 3 50 DATA 5 15 22064 3 51 ELEMENT ELEMENT MASS DATA DATA-ERR 22064 3 52 NO-DIM NO-DIM NO-DIM PC/FIS PC/FIS 22064 3 53 38. 91. 1.48 0.43 22064 3 54 38. 92. 2.09 0.04 22064 3 55 40. 95. 4.04 0.21 22064 3 56 40. 41. 97. 5.16 0.04 22064 3 57 44. 103. 7.65 0.23 22064 3 58 44. 105. 6.85 0.29 22064 3 59 52. 132. 4.70 0.02 22064 3 60 53. 131. 4.01 0.14 22064 3 61 53. 133. 7.46 0.30 22064 3 62 53. 135. 6.09 0.30 22064 3 63 54. 135. 6.80 0.28 22064 3 64 55. 138. 8.48 0.48 22064 3 65 58. 141. 6.29 0.31 22064 3 66 58. 143. 3.48 0.15 22064 3 67 60. 147. 1.81 0.20 22064 3 68 ENDDATA 17 0 22064 3 69 ENDSUBENT 68 0 22064 399999 SUBENT 22064004 20230209 231422064 4 1 BIB 5 8 22064 4 2 REACTION (95-AM-241(N,F),,NU,,,DERIV) 22064 4 3 ANALYSIS nu-bar=242-- 22064 4 4 ERR-ANALYS (DATA-ERR) The errors given are based on errors due to 22064 4 5 gamma-counting and normalization. 22064 4 6 STATUS (TABLE) Abstract of J.Inorg.Nucl.Chem.,33(1971)3239 22064 4 7 (DEP,22064002) 22064 4 8 (DEP,22064003) 22064 4 9 HISTORY (20230209C) SD 22064 4 10 ENDBIB 8 0 22064 4 11 NOCOMMON 0 0 22064 4 12 DATA 2 1 22064 4 13 DATA DATA-ERR 22064 4 14 PRT/FIS PRT/FIS 22064 4 15 4.0 0.2 22064 4 16 ENDDATA 3 0 22064 4 17 ENDSUBENT 16 0 22064 499999 ENDENTRY 4 0 2206499999999