ENTRY 21743 20220205 23092174300000001 SUBENT 21743001 20220205 23092174300100001 BIB 6 13 2174300100002 TITLE Charge distributions in low-energy nuclear fission 2174300100003 and their relevance to fission dynamics 2174300100004 AUTHOR (G.Mariolopoulos,CH.Hamelin,J.Blachot,J.P.Bocquet, 2174300100005 R.Brissot,J.Crancon,H.Nifenecker,CH.Ristori) 2174300100006 INSTITUTE (2FR GRE,2FR ILL) 2174300100007 REFERENCE (J,NP/A,361,213,1981) 2174300100008 (J,NIM,180,141,1981) - Cf -data on figs. 2174300100009 (S,IAEA-SM-241,(F29),1979) 2174300100010 (S,IAEA-SM-241,(F30),1979) 2174300100011 ERR-ANALYS (DATA-ERR) No details given. 2174300100012 HISTORY (19810608C) G.C. 2174300100013 (20220205A) SD:Updated to new date formats,lower case. 2174300100014 Corrections in all Subents. 2174300100015 ENDBIB 13 0 2174300100016 NOCOMMON 0 0 2174300100017 ENDSUBENT 16 0 2174300199999 SUBENT 21743002 20220205 23092174300200001 BIB 11 38 2174300200002 REACTION (92-U-235(N,F)ELEM/MASS,IND,FY,,MXW) 2174300200003 FACILITY (REAC,2FR ILL) HFR 2174300200004 INC-SOURCE (REAC) Neutron guide of the ILL high-flux reactor. 2174300200005 INC-SPECT Thermal Maxwellian neutron spectrum from 2174300200006 high-flux reactor. 2174300200007 SAMPLE 100 mg U(3)-O(8) enriched to 97.68%, 2174300200008 encapsulated in a polyethylene tube. It was 2174300200009 counted at a distance of 3 cm from the Ge(Li)- 2174300200010 detector. 2174300200011 METHOD Gamma counting of the fission products. 2174300200012 Four different methods are used to deduce the 2174300200013 fission yields, 2174300200014 1.) variation of irradiation, cooling and counting 2174300200015 times allows determination of the independent 2174300200016 yield of (A,Z) and the cumulative yield of 2174300200017 (A,Z-1) by linear least squares fitting of 2174300200018 equation 1 of the Nucl.Phys.,A361(1981)213. 2174300200019 2.) Direct estimation of the independent yield of 2174300200020 (A,Z) if the cumulative yield of (A,Z-1) could 2174300200021 be neglected. 2174300200022 3.) Difference between the cumulative yields of 2174300200023 (A,Z) and (A,Z-1). 2174300200024 4.) Determination of the independent yield of 2174300200025 (a,z) from the known value of the cumulative 2174300200026 yield of (A,Z) and an evaluated value of 2174300200027 the cumulative yield of (A,Z-1). 2174300200028 DETECTOR (GELI) 100 cm3, 2.1 keV resolution at 1.4 MeV, 2174300200029 at the end of a fast pneumatic system. 2174300200030 DECAY-DATA ((1.)35-BR-86,,DG,1564.62,0.5356) 2174300200031 ((2.)53-I-134,,DG,847.02,0.9540) 2174300200032 ((3.)54-XE-135,,DG,249.74,0.9060) 2174300200033 ((4.)53-I-136,,DG,381.30,0.9800,DG,1321.10,0.3049) 2174300200034 ((5.)54-XE-137,,DG,455.45,0.3180) 2174300200035 ((6.)57-LA-144,,DG,397.30,0.9033) 2174300200036 MONITOR (92-U-235(N,F)57-LA-144,CUM,FY,,MXW) 2174300200037 (92-U-235(N,F)58-CE-145,CUM,FY,,MXW) 2174300200038 STATUS (TABLE) Tbl.1 from Nucl.Phys.,A361(1981)213 2174300200039 HISTORY (20220205U) SD: STATUS updated. 2174300200040 ENDBIB 38 0 2174300200041 COMMON 1 3 2174300200042 EN-DUMMY 2174300200043 EV 2174300200044 2.5300E-02 2174300200045 ENDCOMMON 3 0 2174300200046 DATA 5 6 2174300200047 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 2174300200048 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 2174300200049 35. 86. 0.65 0.04 1. 2174300200050 53. 134. 1.13 0.12 2. 2174300200051 53. 136. 3.22 0.12 4. 2174300200052 54. 135. 0.33 0.03 3. 2174300200053 54. 137. 3.24 0.07 5. 2174300200054 57. 144. 1.07 0.05 6. 2174300200055 ENDDATA 8 0 2174300200056 ENDSUBENT 55 0 2174300299999 SUBENT 21743003 20220205 23092174300300001 BIB 11 27 2174300300002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 2174300300003 FACILITY (REAC,2FR ILL) 2174300300004 INC-SOURCE (REAC) Neutron guide of the ILL high-flux reactor. 2174300300005 INC-SPECT Thermal Maxwellian neutron spectrum from high-flux 2174300300006 reactor. 2174300300007 SAMPLE 100 mg U(3)-O(8) enriched to 97.68%, 2174300300008 encapsulated in a polyethylene tube. It was counted 2174300300009 at a distance of 3 cm from the Ge(Li)- detector. 2174300300010 METHOD Gamma counting of the fission products. 2174300300011 Variation of irradiation, cooling and counting 2174300300012 times allows determination of the independent 2174300300013 yield of (A,Z) and the cumulative yield of 2174300300014 (A,Z-1) by linear least squares fitting of 2174300300015 equation 1 in Nucl.Phys.,A361(1981)213 2174300300016 DETECTOR (GELI) 100 cm3, 2.1 keV resolution at 1.4 MeV, 2174300300017 at the end of a fast pneumatic system. 2174300300018 DECAY-DATA ((1.)35-BR-88,,DG,802.10,0.1579) 2174300300019 ((2.)36-KR-90,,DG,1118.69,0.3890) 2174300300020 ((3.)38-SR-95,,DG,685.90,0.2400) 2174300300021 ((4.)52-TE-136,,DG,332.60,1.00) 2174300300022 ((5.)55-CS-140,,DG,602.30,0.7000) 2174300300023 ((6.)54-XE-141,,DG,909.39,0.2600) 2174300300024 ((7.)56-BA-144,,DG,388.0,0.6650) 2174300300025 MONITOR (92-U-235(N,F)57-LA-144,CUM,FY,,MXW) 2174300300026 (92-U-235(N,F)58-CE-145,CUM,FY,,MXW) 2174300300027 STATUS (TABLE) Tbl.1 from Nucl.Phys.,A361(1981)213 2174300300028 HISTORY (20220205U) SD: STATUS updated. 2174300300029 ENDBIB 27 0 2174300300030 COMMON 1 3 2174300300031 EN-DUMMY 2174300300032 EV 2174300300033 2.53E-02 2174300300034 ENDCOMMON 3 0 2174300300035 DATA 5 8 2174300300036 ELEMENT MASS DATA DATA-ERR DECAY-FLAG 2174300300037 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 2174300300038 34. 86. 1.26 0.04 2174300300039 35. 88. 1.92 0.10 1. 2174300300040 36. 90. 5.20 0.21 2. 2174300300041 38. 95. 5.47 0.20 3. 2174300300042 52. 136. 1.44 0.10 4. 2174300300043 54. 141. 1.35 0.05 6. 2174300300044 55. 140. 5.70 0.20 5. 2174300300045 56. 144. 4.36 0.05 7. 2174300300046 ENDDATA 10 0 2174300300047 ENDSUBENT 46 0 2174300399999 SUBENT 21743004 20220205 23092174300400001 BIB 11 42 2174300400002 REACTION (92-U-235(N,F)ELEM/MASS,IND,FY,,MXW) 2174300400003 FACILITY (REAC,2FR ILL) for the monitor reaction. 2174300400004 (VDG,2FR ILL) Accelerator SAMES for production of 2174300400005 the 3 MeV neutrons. 2174300400006 INC-SOURCE (REAC) Neutron guide of the ILL high-flux reactor. 2174300400007 (D-D) Deuteron-deuterium reaction for the 2174300400008 production of the 3 MeV neutrons. The purity of 2174300400009 the neutron beam was checked with activation 2174300400010 detectors. Contamination by low energy neutrons 2174300400011 was found to be negligible. 2174300400012 INC-SPECT Thermal Maxwellian neutron spectrum from 2174300400013 HFR, for the monitor reactions. 2174300400014 SAMPLE 100 mg U(3)-O(8) enriched to 97.68%, 2174300400015 encapsulated in a polyethylene tube. It was counted 2174300400016 at a distance of 3 cm from the Ge(Li)- detector. 2174300400017 METHOD Gamma counting of the fission products. 2174300400018 Four different methods are used to deduce the 2174300400019 fission yields, 2174300400020 1.) variation of irradiation, cooling and counting 2174300400021 times allows determination of the independent 2174300400022 yield of (A,Z) and the cumulative yield of 2174300400023 (A,Z-1) by linear least squares fitting of 2174300400024 equation 1 of the Nucl.Phys.,A361(1981)213. 2174300400025 2.) Direct estimation of the independent yield of 2174300400026 (A,Z) if the cumulative yield of (A,Z-1) could 2174300400027 be neglected. 2174300400028 3.) Difference between the cumulative yields of 2174300400029 (A,Z) and (A,Z-1). 2174300400030 4.) determination of the independent yield of 2174300400031 (A,Z) from the known value of the cumulative 2174300400032 yield of (A,Z) and an evaluated value of 2174300400033 the cumulative yield of (A,Z-1). 2174300400034 DETECTOR (GELI) 100 cm3, 2.1 keV resolution at 1.4 MeV, 2174300400035 at the end of a fast pneumatic system. 2174300400036 MONITOR (92-U-235(N,F)57-LA-144,CUM,FY,,MXW) 2174300400037 (92-U-235(N,F)58-CE-145,CUM,FY,,MXW) 2174300400038 FLAG (1.) Method number 1 was used. 2174300400039 (2.) Method number 2 was used. 2174300400040 (3.) Method number 3 was used. 2174300400041 (4.) Method number 4 was used. 2174300400042 STATUS (TABLE) Tbl.3 from Nucl.Phys.,A361(1981)213 2174300400043 HISTORY (20220205U) SD: STATUS updated. 2174300400044 ENDBIB 42 0 2174300400045 COMMON 2 3 2174300400046 EN EN-NRM 2174300400047 MEV EV 2174300400048 3. 2.53E-02 2174300400049 ENDCOMMON 3 0 2174300400050 DATA 6 58 2174300400051 MASS ELEMENT DATA DATA-ERR FLAG FLAG 2174300400052 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM NO-DIM 2174300400053 86. 35. 0.84 0.03 1. 2174300400054 86. 36. 0.17 0.05 3. 2174300400055 87. 35. 1.57 0.08 4. 2174300400056 87. 36. 0.42 0.08 3. 2174300400057 88. 35. 1.85 0.07 4. 2174300400058 88. 36. 1.39 0.1 4. 2174300400059 88. 37. 0.06 0.05 3. 2174300400060 89. 35. 1.36 0.05 4. 2174300400061 89. 36. 2.71 0.25 4. 2174300400062 89. 37. 0.42 0.22 3. 2174300400063 90. 35. 0.635 0.04 2. 2174300400064 90. 36. 3.46 0.15 4. 2174300400065 90. 37. 1.32 0.20 4. 2174300400066 90. 38. 0.03 0.01 4. 2174300400067 91. 35. 0.12 0.04 4. 2174300400068 91. 36. 2.47 0.10 4. 2174300400069 91. 37. 0.23 0.02 4. 2174300400070 93. 36. 0.31 0.02 4. 2174300400071 93. 37. 3.28 0.14 4. 2174300400072 93. 38. 2.33 0.25 3. 2174300400073 93. 39. 0.21 0.20 3. 2174300400074 94. 36. 0.06 0.01 4. 2174300400075 94. 37. 1.81 0.15 2. 2174300400076 94. 38. 3.49 0.20 3. 2174300400077 94. 39. 0.49 0.15 3. 2174300400078 131. 52. 0.63 0.13 3. 2174300400079 132. 51. 2.8 0.2 2174300400080 132. 52. 1.63 0.20 3. 2174300400081 133. 52. 3.83 0.20 3. 2174300400082 134. 52. 4.94 0.1 3. 2174300400083 134. 53. 2.08 0.08 1. 2174300400084 135. 52. 2.02 0.08 4. 2174300400085 135. 53. 3.88 0.28 3. 2174300400086 135. 54. 0.39 0.04 1. 2174300400087 136. 52. 0.85 0.04 1. 2174300400088 136. 53. 3.93 0.12 1. 3.2174300400089 136. 54. 1.40 0.15 3. 2174300400090 136. 55. 0.04 0.01 1. 2174300400091 137. 52. 0.16 0.10 4. 2174300400092 137. 53. 2.38 0.15 1. 4.2174300400093 137. 54. 3.33 0.20 1. 2174300400094 137. 55. 0.31 0.20 3. 2174300400095 138. 53. 1.26 0.06 4. 2174300400096 138. 54. 4.46 0.20 3. 2174300400097 138. 55. 0.81 0.15 1. 2174300400098 139. 53. 0.47 0.03 4. 2174300400099 139. 54. 3.72 0.22 3. 2174300400100 139. 55. 2.14 0.20 4. 2174300400101 140. 54. 2.55 0.13 4. 2174300400102 140. 55. 3.07 0.20 3. 2174300400103 141. 54. 0.62 0.13 4. 2174300400104 142. 55. 2.54 0.12 2. 2174300400105 142. 56. 2.98 0.15 3. 2174300400106 143. 55. 1.21 0.12 4. 2174300400107 143. 56. 3.58 0.15 3. 2174300400108 144. 55. 0.38 0.03 2. 2174300400109 144. 56. 3.01 0.20 3. 2174300400110 144. 57. 1.85 0.12 1. 2174300400111 ENDDATA 60 0 2174300400112 ENDSUBENT 111 0 2174300499999 SUBENT 21743005 20220205 23092174300500001 BIB 10 27 2174300500002 REACTION (92-U-235(N,F)ELEM/MASS,CUM,FY,,MXW) 2174300500003 FACILITY (REAC,2FR ILL) for the monitor reaction. 2174300500004 (VDG,2FR ILL) Accelerator SAMES for production of 2174300500005 the 3 MeV neutrons. 2174300500006 INC-SOURCE (REAC) Neutron guide of the ILL high-flux reactor. 2174300500007 (D-D) Deuteron-deuterium reaction for the 2174300500008 production of the 3 MeV neutrons. The purity of 2174300500009 the neutron beam was checked with activation 2174300500010 detectors. Contamination by low energy neutrons 2174300500011 was found to be negligible. 2174300500012 INC-SPECT Thermal Maxwellian neutron spectrum from 2174300500013 high-flux reactor, for the monitor reactions. 2174300500014 SAMPLE 100 mg U(3)-O(8) enriched to 97.68%, 2174300500015 encapsulated in a polyethylene tube. It was 2174300500016 counted at a distance of 3 cm from the Ge(Li)-detector2174300500017 METHOD Gamma counting of the fission products. 2174300500018 Variation of irradiation, cooling and counting 2174300500019 times allows determination of the independent 2174300500020 yield of (A,Z) and the cumulative yield of 2174300500021 (A,Z-1) by linear least squares fitting of 2174300500022 equation 1 of the Nucl.Phys.,A361(1981)213. 2174300500023 DETECTOR (GELI) 100 cm3, 2.1 keV resolution at 1.4 MeV, 2174300500024 at the end of a fast pneumatic system. 2174300500025 MONITOR (92-U-235(N,F)57-LA-144,CUM,FY,,MXW) 2174300500026 (92-U-235(N,F)58-CE-145,CUM,FY,,MXW) 2174300500027 STATUS (TABLE) Tbl.2 from Nucl.Phys.,A361(1981)213 2174300500028 HISTORY (20220205U) SD: STATUS updated. 2174300500029 ENDBIB 27 0 2174300500030 COMMON 2 3 2174300500031 EN EN-NRM 2174300500032 MEV EV 2174300500033 3.0 2.53E-02 2174300500034 ENDCOMMON 3 0 2174300500035 DATA 4 59 2174300500036 ELEMENT MASS DATA DATA-ERR 2174300500037 NO-DIM NO-DIM PC/FIS PC/FIS 2174300500038 34. 86. 0.92 0.03 2174300500039 35. 86. 0.84 0.03 2174300500040 35. 87. 2.05 0.08 2174300500041 35. 88. 2.03 0.08 2174300500042 35. 90. 0.65 0.10 2174300500043 36. 87. 2.90 0.15 2174300500044 36. 89. 4.41 0.22 2174300500045 36. 90. 4.10 0.05 2174300500046 36. 91. 2.59 0.10 2174300500047 37. 93. 3.59 0.15 2174300500048 37. 94. 1.91 0.13 2174300500049 38. 91. 5.60 0.28 2174300500050 38. 92. 5.85 0.28 2174300500051 38. 93. 5.80 0.28 2174300500052 38. 93. 5.92 0.20 2174300500053 38. 94. 5.70 0.15 2174300500054 38. 95. 5.20 0.30 2174300500055 39. 94. 6.35 0.34 2174300500056 39. 95. 6.40 0.28 2174300500057 40. 97. 5.98 0.24 2174300500058 42. 99. 6.15 0.32 2174300500059 42. 101. 5.05 0.25 2174300500060 43. 102. 4.40 0.22 2174300500061 43. 104. 2.15 0.10 2174300500062 44. 103. 3.48 0.18 2174300500063 44. 105. 1.25 0.06 2174300500064 50. 131. 0.57 0.05 2174300500065 50. 132. 0.49 0.05 2174300500066 51. 127. 0.31 0.02 2174300500067 51. 131. 2.56 0.11 2174300500068 51. 133. 1.82 0.10 2174300500069 51. 134. 0.50 0.08 2174300500070 52. 132. 4.90 0.25 2174300500071 52. 134. 5.37 0.15 2174300500072 52. 135. 2.08 0.08 2174300500073 52. 136. 0.85 0.04 2174300500074 53. 131. 3.95 0.20 2174300500075 53. 133. 6.70 0.33 2174300500076 53. 137. 2.54 0.12 2174300500077 53. 138. 1.27 0.06 2174300500078 53. 139. 0.48 0.03 2174300500079 54. 138. 5.74 0.20 2174300500080 54. 139. 4.20 0.20 2174300500081 54. 140. 2.63 0.10 2174300500082 54. 141. 0.63 0.13 2174300500083 55. 140. 5.70 0.08 2174300500084 55. 142. 2.66 0.10 2174300500085 55. 143. 1.23 0.12 2174300500086 55. 144. 0.38 0.03 2174300500087 56. 140. 6.10 0.20 2174300500088 56. 141. 5.80 0.20 2174300500089 56. 142. 5.64 0.10 2174300500090 56. 143. 4.81 0.10 2174300500091 56. 144. 3.39 0.20 2174300500092 57. 142. 5.80 0.28 2174300500093 58. 143. 5.25 0.28 2174300500094 58. 145. 3.76 0.20 2174300500095 60. 147. 2.26 0.10 2174300500096 61. 151. 0.49 0.02 2174300500097 ENDDATA 61 0 2174300500098 ENDSUBENT 97 0 2174300599999 SUBENT 21743006 20220205 23092174300600001 BIB 8 20 2174300600002 REACTION (98-CF-252(0,F)ELEM,CHG,FY) 2174300600003 SAMPLE A 1.0E+06 fissions/min Cf-252 source, deposited 2174300600004 onto a thin Ni-backing. 2174300600005 METHOD (EDE,COINC) Two categories of events were distinguished2174300600006 The ones where a coincidence occurred between the 2174300600007 X-ray detector and the telescope, and the other 2174300600008 ones. From the coincidences the charge response 2174300600009 functions were deduced. These were used to unfold 2174300600010 the effective charge spectra. 2174300600011 DETECTOR (SOLST) Intrinsic germanium X-ray detector, allowed 2174300600012 to determine the charge of the fission fragments. 2174300600013 (TELES,IOCH,SIBAR) A dE-gas ionization chamber and 2174300600014 a surface barrier as E-detector. 2174300600015 PART-DET (XR) K-alpha X-rays. 2174300600016 (SF) Fission fragments. 2174300600017 CORRECTION Occurence under the K-alpha X-ray peak of K-beta 2174300600018 lines of other elements and gamma-background. 2174300600019 STATUS (TABLE) Tbl.4 from Nucl.Phys.,A361(1981)213 2174300600020 HISTORY (20220205A) SD: SF5=IND -> CHG in REACTION code. 2174300600021 STATUS updated. 2174300600022 ENDBIB 20 0 2174300600023 NOCOMMON 0 0 2174300600024 DATA 3 11 2174300600025 ELEMENT DATA DATA-ERR 2174300600026 NO-DIM PC/FIS PC/FIS 2174300600027 37. 2.0 0.3 2174300600028 38. 2.8 0.3 2174300600029 39. 5.5 0.4 2174300600030 40. 9.5 0.4 2174300600031 41. 11.4 0.5 2174300600032 42. 17.6 0.5 2174300600033 43. 14.4 0.5 2174300600034 44. 16.1 0.5 2174300600035 45. 8.2 0.5 2174300600036 46. 10.0 0.6 2174300600037 47. 2.3 0.3 2174300600038 ENDDATA 13 0 2174300600039 ENDSUBENT 38 0 2174300699999 SUBENT 21743007 20220205 23092174300700001 BIB 11 24 2174300700002 REACTION (90-TH-229(N,F)ELEM,CHG,FY,,MXW) 2174300700003 FACILITY (REAC,2FR ILL) High flux reactor. 2174300700004 INC-SOURCE (REAC) Neutron guide of the high flux reactor. 2174300700005 INC-SPECT Thermal Maxwellian neutron spectrum from 2174300700006 High flux reactor. 2174300700007 SAMPLE Th-229 target, 30 ug thick, deposited 2174300700008 over 1 cm**2 on a Be-backing. 2174300700009 METHOD (COINC) Two categories of events were distinguished. 2174300700010 The ones were a coincidence occurred between the 2174300700011 X-ray detector and the telescope, and the other 2174300700012 ones. From the coincidences the charge response 2174300700013 functions were deduced. These were used to unfold 2174300700014 the effective charge spectra. 2174300700015 DETECTOR (GE) Intrinsic germanium X-ray detector. It allowed to 2174300700016 determine the charge of the fission fragment. 2174300700017 (TELES,IOCH,SIBAR) A dE-gas ionization chamber 2174300700018 and a surface barrier as E-detector. 2174300700019 PART-DET (XR) K-alpha X-rays in coincidence with 2174300700020 (FF) fission fragments. 2174300700021 CORRECTION Occurence of K-beta lines from other elements and 2174300700022 gamma background under the K-alpha X-ray peak. 2174300700023 STATUS (TABLE) Tbl.4 from Nucl.Phys.,A361(1981)213 2174300700024 HISTORY (20220205A) SD: SF5=IND -> CHG in REACTION code. 2174300700025 STATUS updated. 2174300700026 ENDBIB 24 0 2174300700027 COMMON 1 3 2174300700028 EN-DUMMY 2174300700029 EV 2174300700030 2.53E-02 2174300700031 ENDCOMMON 3 0 2174300700032 DATA 3 9 2174300700033 ELEMENT DATA DATA-ERR 2174300700034 NO-DIM PC/FIS PC/FIS 2174300700035 32. 5.2 0.4 2174300700036 33. 4.3 0.4 2174300700037 34. 27.7 0.7 2174300700038 35. 12.8 0.8 2174300700039 36. 22.6 0.6 2174300700040 37. 12.3 0.7 2174300700041 38. 10. 0.5 2174300700042 39. 3.2 0.6 2174300700043 40. 2.0 0.6 2174300700044 ENDDATA 11 0 2174300700045 ENDSUBENT 44 0 2174300799999 ENDENTRY 7 0 2174399999999