ENTRY 10930 20170822 14331093000000001 SUBENT 10930001 20170822 14331093000100001 BIB 10 33 1093000100002 TITLE Prompt Neutron Multiplicity Distribution in the 1093000100003 Spontaneous Fission of Curium-242 1093000100004 AUTHOR (J.Halperin,C.E.Bemis JR,J.W.T.Dabbs,B.H.Ketelle, 1093000100005 R.W.Stoughton,R.W.Hoff,R.J.Dougan) 1093000100006 REFERENCE (J,NSE,75,56,1980) 1093000100007 (J,BAP,25,487,1980) 1093000100008 INSTITUTE (1USAORL,1USALRL) 1093000100009 DETECTOR (PROPC) Fission neutrons counted with 30 helium-3 1093000100010 detectors, 2.5-cm diameter, 60-cm long, 6-atm 1093000100011 pressure, embedded in a cylindrical paraffin and 1093000100012 polyethylene matrix, 54-cm diameter, 90-cm long. 1093000100013 (FISCH) Gas filled counter with hemispherical 1093000100014 geometry. Active sample deposited on convex surface, 1093000100015 electron charge collected on concentric surface 2-mm 1093000100016 from source. 1093000100017 METHOD (COINC) Fission chamber inserted into a 10-cm 1093000100018 diameter hole that penetrates central core of 1093000100019 paraffin-polyethylene cylinder. Helium-3 counters 1093000100020 placed parallel to cylinder axis, spaced symmetrically 1093000100021 into 3 concentric rings. Fission of known Cf-252 1093000100022 sample used to calibrate He-3 counters. A pulse from 1093000100023 a fission chamber serves to open a gate to count 1093000100024 nearly all neutrons detected in coincidence with the 1093000100025 fission fragment. 1093000100026 MONITOR (98-CF-252(0,F),PR,NU) 1093000100027 CORRECTION Corrections made for background neutrons and 1093000100028 accidentals. Contributions to spontaneous fission 1093000100029 rates by impurities not corrected for. 1093000100030 STATUS (APRVD) Approved by J.Halperin, 1981/2/12. 1093000100031 HISTORY (19801201C) 1093000100032 (20170822A) BP: Updated to new date formats,lower 1093000100033 case. Corrections according last EXFOR rules and 1093000100034 Dict. Added fission neutron multiplicity distribution. 1093000100035 ENDBIB 33 0 1093000100036 COMMON 1 3 1093000100037 MONIT 1093000100038 PRT/FIS 1093000100039 3.760 1093000100040 ENDCOMMON 3 0 1093000100041 ENDSUBENT 40 0 1093000199999 SUBENT 10930002 20170822 14331093000200001 BIB 6 9 1093000200002 REACTION (96-CM-242(0,F),PR,NU) 1093000200003 SAMPLE Cm-242 formed from the radioactive decay of Am-242. 1093000200004 ERR-ANALYS (DATA-ERR) Quoted error includes counting statistics 1093000200005 and systematic uncertainties. 1093000200006 DECAY-DATA (95-AM-242-G,16.02HR,B-) 1093000200007 (96-CM-242,162.8D,A) 1093000200008 STATUS (TABLE) page 59. 1093000200009 HISTORY (19820108A) Corrected reaction, monitor. 1093000200010 (20170822A) BP: Corrected units. 1093000200011 ENDBIB 9 0 1093000200012 NOCOMMON 0 0 1093000200013 DATA 2 1 1093000200014 DATA DATA-ERR 1093000200015 PRT/FIS PRT/FIS 1093000200016 2.532 0.013 1093000200017 ENDDATA 3 0 1093000200018 ENDSUBENT 17 0 1093000299999 SUBENT 10930003 20170822 14331093000300001 BIB 7 8 1093000300002 REACTION (96-CM-242(0,F),PR/NUM,NU) 1093000300003 SAMPLE Cm-242 formed from the radioactive decay of Am-242. 1093000300004 ERR-ANALYS (ERR-S) Counting statistics only. 1093000300005 FLAG (1.) Multiplicity 7 is used for 7 and more neutrons. 1093000300006 DECAY-DATA (95-AM-242-G,16.02HR,B-) 1093000300007 (96-CM-242,162.8D,A) 1093000300008 STATUS (TABLE) Table II, page 59. 1093000300009 HISTORY (20170822C) BP 1093000300010 ENDBIB 8 0 1093000300011 NOCOMMON 0 0 1093000300012 DATA 4 8 1093000300013 PART-OUT DATA ERR-S FLAG 1093000300014 NO-DIM NO-DIM NO-DIM NO-DIM 1093000300015 0. 0.27695 0.00069 1093000300016 1. 0.41220 0.00084 1093000300017 2. 0.23595 0.00064 1093000300018 3. 0.06498 0.00033 1093000300019 4. 0.008559 0.000115 1093000300020 5. 0.000549 0.000026 1093000300021 6. 0.000016 0.000004 1093000300022 7. 0.0000002 0.0000002 1. 1093000300023 ENDDATA 10 0 1093000300024 ENDSUBENT 23 0 1093000399999 SUBENT 10930004 20170822 14331093000400001 BIB 6 8 1093000400002 REACTION (98-CF-252(0,F),PR/NUM,NU) 1093000400003 SAMPLE (98-CF-252,ENR=0.995) Isotopically pure 252Cf was 1093000400004 deposited with an ion accelerator 400 A beneath the 1093000400005 surface of an aluminum foil. 1093000400006 ERR-ANALYS (ERR-S) Counting statistics only. 1093000400007 FLAG (1.) Multiplicity 7 is used for 7 and more neutrons. 1093000400008 STATUS (TABLE) Table II, page 59. 1093000400009 HISTORY (20170822C) BP 1093000400010 ENDBIB 8 0 1093000400011 NOCOMMON 0 0 1093000400012 DATA 4 8 1093000400013 PART-OUT DATA ERR-S FLAG 1093000400014 NO-DIM NO-DIM NO-DIM NO-DIM 1093000400015 0. 0.14366 0.00072 1093000400016 1. 0.33167 0.00109 1093000400017 2. 0.31444 0.00107 1093000400018 3. 0.15708 0.00075 1093000400019 4. 0.04453 0.00040 1093000400020 5. 0.00723 0.00015 1093000400021 6. 0.000644 0.000040 1093000400022 7. 0.000026 0.000007 1. 1093000400023 ENDDATA 10 0 1093000400024 ENDSUBENT 23 0 1093000499999 ENDENTRY 4 0 1093099999999