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