ENTRY 14625 20200526 14691462500000001 SUBENT 14625001 20200526 14691462500100001 BIB 14 44 1462500100002 TITLE Radiochemical studies of the fast neutron fission of 1462500100003 uranium-235 and uranium-238 1462500100004 AUTHOR (L.R.Bunney,E.M.Scadden,J.O.Abriam,N.E.Ballou) 1462500100005 REFERENCE (C,58GENEVA,15,449,1958) 1462500100006 INSTITUTE (1USANRD) 1462500100007 FACILITY (CYCLO,1USACLA) The 60-in. cyclotron at the 1462500100008 University of California 1462500100009 SAMPLE The targets were stacks of uranium foil which had 1462500100010 been enriched (93.5% U235) or depleted (0.031% U235) 1462500100011 in U235. These foil stacks were enclosed in cadmium 1462500100012 sheet 0.75-mm thick to filter out the thermal neutrons 1462500100013 present. These target assemblies were placed in the 1462500100014 cyclotron behind a beryllium target. 1462500100015 DETECTOR (PROPC) Side-window, gas-flow, proportional counters. 1462500100016 METHOD (CHSEP,ACTIV) After irradiation, the uranium foils were1462500100017 dissolved in 6 N HNO3. The final precipitates were 1462500100018 collected on 23-mm filter paper. A filter tower was 1462500100019 used, which defined a sample area 20 mm in diameter. 1462500100020 The filter papers were mounted on brass planchets 1462500100021 3/8-in. thick and covered with thin pliofilm (about 1462500100022 1 mg/cm2). 1462500100023 ANALYSIS (DECAY) 1462500100024 ERR-ANALYS No information on uncertainty. The precision of the 1462500100025 radiochemical analyses is about 5%. 1462500100026 CORRECTION The counting rates were corrected for chemical yield, 1462500100027 decay from the end of the irradiation to the time of 1462500100028 counting, the length of irradiation, and the counting 1462500100029 shelf if it differed from the "standard" shelf. 1462500100030 An empirical correction for self-scattering and 1462500100031 self-absorption was made by plotting observed specific 1462500100032 activity vs. sample weight for samples made up from the1462500100033 same solution of each radionuclide of interest and 1462500100034 normalizing to a convenient sample weight. In this way 1462500100035 these corrections were kept smaller than 10% in all 1462500100036 cases. 1462500100037 DECAY-DATA ((2.)58-CE-144,280.D) 1462500100038 ((3.)60-ND-147,11.1D) 1462500100039 ((4.)61-PM-149,53.HR) 1462500100040 ((5.)62-SM-153,47.HR) 1462500100041 ((6.)63-EU-156,15.4D) 1462500100042 ((7.)64-GD-159,18.HR) 1462500100043 ((8.)65-TB-161,6.8D) 1462500100044 DECAY-MON (42-MO-99,66.2HR) 1462500100045 HISTORY (20200325C) OG. 1462500100046 ENDBIB 44 0 1462500100047 NOCOMMON 0 0 1462500100048 ENDSUBENT 47 0 1462500199999 SUBENT 14625002 20200526 14691462500200001 BIB 5 8 1462500200002 REACTION 1(92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1-st sample 1462500200003 2(92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 2-nd sample 1462500200004 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1462500200005 INC-SOURCE (P-BE) Beryllium target irradiated with 12-MeV protons.1462500200006 INC-SPECT A neutron spectrum approximates fairly well that of 1462500200007 fission neutrons (compiler's remark: with the maximum 1462500200008 energy of the distribution at about 0.7 MeV). 1462500200009 STATUS (TABLE) Tab.1 (p.450) in At.En.Conf.,Geneva,15,449,19581462500200010 ENDBIB 8 0 1462500200011 COMMON 2 3 1462500200012 EN-DUMMY MONIT 1462500200013 MEV PC/FIS 1462500200014 0.7 6.1 1462500200015 ENDCOMMON 3 0 1462500200016 DATA 5 7 1462500200017 ELEMENT MASS DATA 1DATA 2DECAY-FLAG 1462500200018 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 1462500200019 58. 144. 5.3 5.1 2. 1462500200020 60. 147. 2.4 2.5 3. 1462500200021 61. 149. 1.3 1.3 4. 1462500200022 62. 153. 0.18 0.19 5. 1462500200023 63. 156. 0.023 0.023 6. 1462500200024 64. 159. 0.0030 0.0038 7. 1462500200025 65. 161. 0.00045 0.00046 8. 1462500200026 ENDDATA 9 0 1462500200027 ENDSUBENT 26 0 1462500299999 SUBENT 14625003 20200526 14691462500300001 BIB 5 7 1462500300002 REACTION 1(92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 1-st sample 1462500300003 2(92-U-235(N,F)ELEM/MASS,CUM,FY,,SPA) 2-nd sample 1462500300004 MONITOR (92-U-235(N,F)42-MO-99,CUM,FY) 1462500300005 INC-SOURCE (D-BE) Be target irradiated with 24-MeV deuterons. 1462500300006 INC-SPECT A neutron spectrum has an energy with the maximum of 1462500300007 the distribution at about 8 MeV. 1462500300008 STATUS (TABLE) Tab.1 (p.450) in At.En.Conf.,Geneva,15,449,19581462500300009 ENDBIB 7 0 1462500300010 COMMON 2 3 1462500300011 EN-DUMMY MONIT 1462500300012 MEV PC/FIS 1462500300013 8. 5.4 1462500300014 ENDCOMMON 3 0 1462500300015 DATA 5 7 1462500300016 ELEMENT MASS DATA 1DATA 2DECAY-FLAG 1462500300017 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 1462500300018 58. 144. 3.2 4.0 2. 1462500300019 60. 147. 1.9 2.2 3. 1462500300020 61. 149. 1.3 1.2 4. 1462500300021 62. 153. 0.18 0.19 5. 1462500300022 63. 156. 0.035 0.035 6. 1462500300023 64. 159. 0.0068 0.0058 7. 1462500300024 65. 161. 0.0019 0.0020 8. 1462500300025 ENDDATA 9 0 1462500300026 ENDSUBENT 25 0 1462500399999 SUBENT 14625004 20200526 14691462500400001 BIB 5 8 1462500400002 REACTION 1(92-U-238(N,F)ELEM/MASS,CUM,FY,,SPA) 1-st sample 1462500400003 2(92-U-238(N,F)ELEM/MASS,CUM,FY,,SPA) 2-nd sample 1462500400004 MONITOR (92-U-238(N,F)42-MO-99,CUM,FY) 1462500400005 INC-SOURCE (P-BE) Beryllium target irradiated with 12-MeV protons.1462500400006 INC-SPECT A neutron spectrum approximates fairly well that of 1462500400007 fission neutrons (compiler's remark: with the maximum 1462500400008 energy of the distribution at about 0.7 MeV). 1462500400009 STATUS (TABLE) Tab.1 (p.450) in At.En.Conf.,Geneva,15,449,19581462500400010 ENDBIB 8 0 1462500400011 COMMON 2 3 1462500400012 EN-DUMMY MONIT 1462500400013 MEV PC/FIS 1462500400014 0.7 6.2 1462500400015 ENDCOMMON 3 0 1462500400016 DATA 5 7 1462500400017 ELEMENT MASS DATA 1DATA 2DECAY-FLAG 1462500400018 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 1462500400019 58. 144. 4.0 4.4 2. 1462500400020 60. 147. 2.6 2.9 3. 1462500400021 61. 149. 2.2 2.0 4. 1462500400022 62. 153. 0.39 0.37 5. 1462500400023 63. 156. 0.073 0.066 6. 1462500400024 64. 159. 0.0095 0.0077 7. 1462500400025 65. 161. 0.0016 0.0016 8. 1462500400026 ENDDATA 9 0 1462500400027 ENDSUBENT 26 0 1462500499999 SUBENT 14625005 20200526 14691462500500001 BIB 5 7 1462500500002 REACTION 1(92-U-238(N,F)ELEM/MASS,CUM,FY,,SPA) 1-st sample 1462500500003 2(92-U-238(N,F)ELEM/MASS,CUM,FY,,SPA) 2-nd sample 1462500500004 MONITOR (92-U-238(N,F)42-MO-99,CUM,FY) 1462500500005 INC-SOURCE (D-BE) Be target irradiated with 24-MeV deuterons. 1462500500006 INC-SPECT A neutron spectrum has an energy with the maximum of 1462500500007 the distribution at about 8 MeV. 1462500500008 STATUS (TABLE) Tab.1 (p.450) in At.En.Conf.,Geneva,15,449,19581462500500009 ENDBIB 7 0 1462500500010 COMMON 2 3 1462500500011 EN-DUMMY MONIT 1462500500012 MEV PC/FIS 1462500500013 8. 6.2 1462500500014 ENDCOMMON 3 0 1462500500015 DATA 5 7 1462500500016 ELEMENT MASS DATA 1DATA 2DECAY-FLAG 1462500500017 NO-DIM NO-DIM PC/FIS PC/FIS NO-DIM 1462500500018 58. 144. 3.9 4.3 2. 1462500500019 60. 147. 2.7 2.7 3. 1462500500020 61. 149. 1.9 4. 1462500500021 62. 153. 0.41 0.41 5. 1462500500022 63. 156. 0.092 0.087 6. 1462500500023 64. 159. 0.018 0.016 7. 1462500500024 65. 161. 0.0044 0.0041 8. 1462500500025 ENDDATA 9 0 1462500500026 ENDSUBENT 25 0 1462500599999 ENDENTRY 5 0 1462599999999