ENTRY 40547 20210623 41964054700000001
SUBENT 40547001 20210623 41964054700100001
BIB 9 53 4054700100002
TITLE Absolute fission cross section of heavy elements 4054700100003
by fast neutrons 4054700100004
AUTHOR (V.M.Adamov, B.M.Aleksandrov, I.D.Alkhazov, 4054700100005
L.V.Drapchinskiy, S.S.Kovalenko, O.I.Kostochkin, 4054700100006
G.Ju.Kudryavcev, L.Z.Malkin, K.A.Petrzhak, 4054700100007
L.A.Pleskachevskiy, A.V.Fomichev, V.I.Shpakov) 4054700100008
INSTITUTE (4RUSRI) 4054700100009
REFERENCE ((R,YK-24,8,1977)=(R,INDC(CCP)-114,8,1977)) 4054700100010
Preliminary data compiled in 002-009 4054700100011
(C,79KNOX,,995,1979) 4054700100012
Revised data compiled in 010-017 4054700100013
(P,ZFK-503,11,1983) 4054700100014
233U 14 MeV data identical to 79KNOX,,995 4054700100015
(R,YFI-23,17,1977) 4054700100016
Data identical to those in YK-24,8 4054700100017
(C,77NBS,,313,1977) 4054700100018
235,238U PFNS data identical to those in YK-24,8 4054700100019
((C,77KIEV,3,155,1977)=(R,INDC(CCP)-118,(3),155,1977)) 4054700100020
233U,239Pu 14 MeV data identical to those in YK-24,8 4054700100021
((C,77KIEV,3,158,1977)=(R,INDC(CCP)-118,(3),158,1977)) 4054700100022
233U,239Pu PFNS data identical to those in YK-24,8 4054700100023
(R,YFI-22,12,1976) 4054700100024
233U,239Pu 14 MeV data identical to those in YK-24,8 4054700100025
(but with minor difference in uncertainties) 4054700100026
(R,INDC(CCP)-100,10,1977) 4054700100027
English translation of YFI-22,12,1976 4054700100028
(R,YFI-22,14,1976) 4054700100029
235,238U PFNS data identical to those in YK-24,8 4054700100030
(R,INDC(CCP)-100,13,1977) 4054700100031
English translation of YFI-22,14,1976 4054700100032
((C,75KIEV,6,19,1975)=(R,INDC(CCP)-099,(6),19,1975)) 4054700100033
235,238U PFNS data (235U=1265(19) mb, 238U data 4054700100034
identical to those in YK-24,8 4054700100035
REL-REF (O,40553001,V.M.Adamov+,C,77KIEV,3,158,1977) 4054700100036
237Np PFNS data 4054700100037
(O,40552003,I.D.Alkhazov+,C,77KIEV,3,155,1977) 4054700100038
237Np 14 MeV data 4054700100039
DETECTOR (FISCH) Double ionization chamber for fragments 4054700100040
(SCIN,SIBAR) Plastic scintillation and surface-barrier4054700100041
silicon detector for alpha-particles 4054700100042
METHOD (COINC) 4054700100043
COMMENT Work partly supported by IAEA Research Contract 1718/RB4054700100044
HISTORY (19781219C) Compiled at the CJD 4054700100045
(19861021A) Data assigned as fundamental, data-errors 4054700100046
structure is given for all elements 4054700100047
(20060801A) ERR-T was corrected. M.M. 4054700100048
(20191213A) Ref. C,77NBS,313,1977 added. 4054700100049
BIB information updated. INDC(CCP) refs. added. 4054700100050
kT value was corrected 1.42 -> 1.406 MeV 4054700100051
- as mentioned in rep.YFI-22,12,1977 on page 15. 4054700100052
(20201104A) On. 002-009 superseded. 010-017 added. 4054700100053
(20201109A) M.M. Subents 018-024 were added. 4054700100054
(20210623A) On. Major revision in 017. 4054700100055
ENDBIB 53 0 4054700100056
NOCOMMON 0 0 4054700100057
ENDSUBENT 56 0 4054700199999
SUBENT 40547002 20201109 41934054700200001
BIB 7 18 4054700200002
REACTION (92-U-233(N,F),,SIG,,FIS) 4054700200003
INC-SOURCE (CF252) 4054700200004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054700200005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments 4054700200006
ERR-ANALYS (ERR-T) Total uncertainty (1.60%)4054700200007
(ERR-1) 252Cf nu-bar (0.35%)4054700200008
(ERR-2) geometrical factor (0.71%)4054700200009
(ERR-3) sample weight- solid angle of camera (0.3%)4054700200010
(ERR-4) sample weight- statistics (0.56%)4054700200011
(ERR-5) sample weight- isotopic fraction (0.2%)4054700200012
(ERR-6) sample weight- isotope half-life (0.28%)4054700200013
(ERR-7) fission -statistics (0.97%)4054700200014
(ERR-10) fission -extrapolation to 0-energy (0.43%)4054700200015
(ERR-11) fission -fragment absorption in a layer(0.35%)4054700200016
(ERR-12) fission -impurity fission (0.21%)4054700200017
STATUS (TABLE) Tables 1 (error) +3 (data) of YK-24,8,1977 4054700200018
(SPSDD,40547010) improved method for geometrical factor4054700200019
HISTORY (20201104A) On. Superseded. ERR-ANALYS revised. 4054700200020
ENDBIB 18 0 4054700200021
COMMON 10 6 4054700200022
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4054700200023
ERR-7 ERR-10 ERR-11 ERR-12 4054700200024
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700200025
PER-CENT PER-CENT PER-CENT PER-CENT 4054700200026
0.35 0.71 0.3 0.56 0.2 0.28 4054700200027
0.97 0.43 0.35 0.21 4054700200028
ENDCOMMON 6 0 4054700200029
DATA 3 1 4054700200030
KT DATA ERR-T 4054700200031
MEV MB MB 4054700200032
1.406 1947. 31. 4054700200033
ENDDATA 3 0 4054700200034
ENDSUBENT 33 0 4054700299999
SUBENT 40547003 20201109 41934054700300001
BIB 8 20 4054700300002
REACTION (92-U-233(N,F),,SIG) 4054700300003
FACILITY (CCW) 4054700300004
INC-SOURCE (D-T) 4054700300005
METHOD (ASSOP) Detection of fission fragments and alpha 4054700300006
PART-DET (FF,A) 4054700300007
ERR-ANALYS (ERR-T) Total uncertainty (1.80%)4054700300008
(ERR-3) sample weight- solid angle of camera (0.3%)4054700300009
(ERR-4) sample weight- statistics (0.56%)4054700300010
(ERR-5) sample weight- isotopic fraction (0.2%)4054700300011
(ERR-6) sample weight- isotope half-life (0.29%)4054700300012
(ERR-7) fission- statistics (1.0%)4054700300013
(ERR-8) fission- random coincidence (0.2%)4054700300014
(ERR-9) fission- neutron flux loss (1.0%)4054700300015
(ERR-10) fission- extrapolation to 0-energy (0.45%)4054700300016
(ERR-11) fission- fragment absorption in a layer(0.35%)4054700300017
(ERR-12) fission- impurity fission (0.45%)4054700300018
(ERR-13) number of associated particle (0.05%)4054700300019
STATUS (TABLE) Tables 2 (error) +3 (data) of YK-24,8,1977 4054700300020
(SPSDD,40547011) improved finite geometry correction 4054700300021
HISTORY (20201104A) On. Superseded. ERR-ANALYS revised. 4054700300022
ENDBIB 20 0 4054700300023
COMMON 11 6 4054700300024
ERR-3 ERR-4 ERR-5 ERR-6 ERR-7 ERR-8 4054700300025
ERR-9 ERR-10 ERR-11 ERR-12 ERR-13 4054700300026
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700300027
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700300028
0.3 0.56 0.2 0.29 1.0 0.2 4054700300029
1.0 0.45 0.35 0.45 0.05 4054700300030
ENDCOMMON 6 0 4054700300031
DATA 3 1 4054700300032
EN DATA ERR-T 4054700300033
MEV MB MB 4054700300034
14.8 2350. 42. 4054700300035
ENDDATA 3 0 4054700300036
ENDSUBENT 35 0 4054700399999
SUBENT 40547004 20201109 41934054700400001
BIB 7 18 4054700400002
REACTION (92-U-235(N,F),,SIG,,FIS) 4054700400003
INC-SOURCE (CF252) 4054700400004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054700400005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments 4054700400006
ERR-ANALYS (ERR-T) Total uncertainty (1.44%)4054700400007
(ERR-1) 252Cf nu-bar (0.35%)4054700400008
(ERR-2) geometrical factor (0.71%)4054700400009
(ERR-3) sample weight- solid angle of camera (0.3%)4054700400010
(ERR-4) sample weight- statistics (0.35%)4054700400011
(ERR-5) sample weight- isotopic fraction (0.41%)4054700400012
(ERR-6) sample weight- isotope half-life (0.20%)4054700400013
(ERR-7) fission -statistics (0.8%)4054700400014
(ERR-10) fission -extrapolation to 0-energy (0.40%)4054700400015
(ERR-11) fission -fragment absorption in a layer (0.3%)4054700400016
(ERR-12) fission -impurity fission (0.30%)4054700400017
STATUS (TABLE) Tables 1 (error) +3 (data) of YK-24,8,1977 4054700400018
(SPSDD,40547012) improved method for geometrical factor4054700400019
HISTORY (20201104A) On. Superseded. ERR-ANALYS revised. 4054700400020
ENDBIB 18 0 4054700400021
COMMON 10 6 4054700400022
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4054700400023
ERR-7 ERR-10 ERR-11 ERR-12 4054700400024
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700400025
PER-CENT PER-CENT PER-CENT PER-CENT 4054700400026
0.35 0.71 0.3 0.35 0.41 0.20 4054700400027
0.8 0.40 0.3 0.30 4054700400028
ENDCOMMON 6 0 4054700400029
DATA 3 1 4054700400030
KT DATA ERR-T 4054700400031
MEV MB MB 4054700400032
1.406 1266. 19. 4054700400033
ENDDATA 3 0 4054700400034
ENDSUBENT 33 0 4054700499999
SUBENT 40547005 20201109 41934054700500001
BIB 8 20 4054700500002
REACTION (92-U-235(N,F),,SIG) 4054700500003
FACILITY (CCW) 4054700500004
INC-SOURCE (D-T) 4054700500005
METHOD (ASSOP) Detection of fission fragments and alpha 4054700500006
PART-DET (FF,A) 4054700500007
ERR-ANALYS (ERR-T) Total uncertainty (1.60%)4054700500008
(ERR-3) sample weight- solid angle of camera (0.3%)4054700500009
(ERR-4) sample weight- statistics (0.35%)4054700500010
(ERR-5) sample weight- isotopic fraction (0.41%)4054700500011
(ERR-6) sample weight- isotope half-life (0.20%)4054700500012
(ERR-7) fission- statistics (1.0%)4054700500013
(ERR-8) fission- random coincidence (0.2%)4054700500014
(ERR-9) fission- neutron flux loss (1.0%)4054700500015
(ERR-10) fission- extrapolation to 0-energy (0.40%)4054700500016
(ERR-11) fission- fragment absorption in a layer(0.30%)4054700500017
(ERR-12) fission- impurity fission (0.20%)4054700500018
(ERR-13) number of associated particle (0.05%)4054700500019
STATUS (TABLE) Tables 2 (error) +3 (data) of YK-24,8,1977 4054700500020
(SPSDD,40547013) improved finite geometry correction 4054700500021
HISTORY (20201104A) On. Superseded. ERR-ANALYS revised. 4054700500022
ENDBIB 20 0 4054700500023
COMMON 11 6 4054700500024
ERR-3 ERR-4 ERR-5 ERR-6 ERR-7 ERR-8 4054700500025
ERR-9 ERR-10 ERR-11 ERR-12 ERR-13 4054700500026
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700500027
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700500028
0.3 0.35 0.41 0.20 1.0 0.2 4054700500029
1.0 0.40 0.30 0.20 0.05 4054700500030
ENDCOMMON 6 0 4054700500031
DATA 3 1 4054700500032
EN DATA ERR-T 4054700500033
MEV MB MB 4054700500034
14.8 2188. 37. 4054700500035
ENDDATA 3 0 4054700500036
ENDSUBENT 35 0 4054700599999
SUBENT 40547006 20201109 41934054700600001
BIB 7 18 4054700600002
REACTION (92-U-238(N,F),,SIG,,FIS) 4054700600003
INC-SOURCE (CF252) 4054700600004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054700600005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments 4054700600006
ERR-ANALYS (ERR-T) Total uncertainty (1.68%)4054700600007
(ERR-1) 252Cf nu-bar (0.35%)4054700600008
(ERR-2) geometrical factor (0.71%)4054700600009
(ERR-3) sample weight- statistics (0.55%)4054700600010
(ERR-4) sample weight- extrapolation to 0-energy(0.51%)4054700600011
(ERR-5) sample weight- absorption and scattering(0.30%)4054700600012
(ERR-6) sample weight- isotopic fraction (0.30%)4054700600013
(ERR-7) fission -statistics (1.11%)4054700600014
(ERR-10) fission -extrapolation to 0-energy (0.37%)4054700600015
(ERR-11) fission -fragment absorption in a layer(0.25%)4054700600016
(ERR-12) fission -impurity fission (0.14%)4054700600017
STATUS (TABLE) Tables 1 (error) +3 (data) of YK-24,8,1977 4054700600018
(SPSDD,40547014) improved method for geometrical factor4054700600019
HISTORY (20201104A) On. Superseded. ERR-ANALYS revised. 4054700600020
ENDBIB 18 0 4054700600021
COMMON 10 6 4054700600022
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4054700600023
ERR-7 ERR-10 ERR-11 ERR-12 4054700600024
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700600025
PER-CENT PER-CENT PER-CENT PER-CENT 4054700600026
0.35 0.71 0.55 0.51 0.30 0.30 4054700600027
1.11 0.37 0.25 0.14 4054700600028
ENDCOMMON 6 0 4054700600029
DATA 3 1 4054700600030
KT DATA ERR-T 4054700600031
MEV MB MB 4054700600032
1.406 347. 6. 4054700600033
ENDDATA 3 0 4054700600034
ENDSUBENT 33 0 4054700699999
SUBENT 40547007 20201109 41934054700700001
BIB 8 21 4054700700002
REACTION (92-U-238(N,F),,SIG) 4054700700003
FACILITY (CCW) 4054700700004
INC-SOURCE (D-T) 4054700700005
METHOD (ASSOP) Detection of fission fragments and alpha 4054700700006
PART-DET (FF,A) 4054700700007
ERR-ANALYS (ERR-T) Total uncertainty (1.70%)4054700700008
(ERR-2) sample weight- half-life (0.20%)4054700700009
(ERR-3) sample weight- statistics (0.55%)4054700700010
(ERR-4) sample weight- extrapolation to 0-energy(0.51%)4054700700011
(ERR-5) sample weight- absorption and scattering(0.30%)4054700700012
(ERR-6) sample weight- isotopic fraction (0.10%)4054700700013
(ERR-7) fission- statistics (1.0%)4054700700014
(ERR-8) fission- random coincidence (0.2%)4054700700015
(ERR-9) fission- neutron flux loss (1.0%)4054700700016
(ERR-10) fission- extrapolation to 0-energy (0.20%)4054700700017
(ERR-11) fission- fragment absorption in a layer(0.30%)4054700700018
(ERR-12) fission- impurity fission (0.12%)4054700700019
(ERR-13) number of associated particle (0.03%)4054700700020
STATUS (TABLE) Tables 2 (error) +3 (data) of YK-24,8,1977 4054700700021
(SPSDD,40547015) improved finite geometry correction 4054700700022
HISTORY (20201104A) On. Superseded. ERR-ANALYS revised. 4054700700023
ENDBIB 21 0 4054700700024
COMMON 12 6 4054700700025
ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 ERR-7 4054700700026
ERR-8 ERR-9 ERR-10 ERR-11 ERR-12 ERR-13 4054700700027
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700700028
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700700029
0.20 0.55 0.51 0.30 0.10 1.0 4054700700030
0.2 1.0 0.20 0.30 0.12 0.03 4054700700031
ENDCOMMON 6 0 4054700700032
DATA 3 1 4054700700033
EN DATA ERR-T 4054700700034
MEV MB MB 4054700700035
14.8 1207. 20. 4054700700036
ENDDATA 3 0 4054700700037
ENDSUBENT 36 0 4054700799999
SUBENT 40547008 20201109 41934054700800001
BIB 7 18 4054700800002
REACTION (94-PU-239(N,F),,SIG,,FIS) 4054700800003
INC-SOURCE (CF252) 4054700800004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054700800005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments 4054700800006
ERR-ANALYS (ERR-T) Total uncertainty (1.62%)4054700800007
(ERR-1) 252Cf nu-bar (0.35%)4054700800008
(ERR-2) geometrical factor (0.71%)4054700800009
(ERR-3) sample weight- solid angle of camera (0.3%) 4054700800010
(ERR-4) sample weight- statistics (0.43%)4054700800011
(ERR-5) sample weight- isotopic fraction (0.34%)4054700800012
(ERR-6) sample weight- isotope half-life (0.12%)4054700800013
(ERR-7) fission -statistics (0.62%)4054700800014
(ERR-10) fission -extrapolation to 0-energy (0.58%)4054700800015
(ERR-11) fission -fragment absorption in a layer(0.61%)4054700800016
(ERR-12) fission -impurity fission (0.71%)4054700800017
STATUS (TABLE) Tables 1 (error) +3 (data) of YK-24,8,1977 4054700800018
(SPSDD,40547016) improved method for geometrical factor4054700800019
HISTORY (20201104A) On. Superseded. ERR-ANALYS revised. 4054700800020
ENDBIB 18 0 4054700800021
COMMON 10 6 4054700800022
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4054700800023
ERR-7 ERR-10 ERR-11 ERR-12 4054700800024
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700800025
PER-CENT PER-CENT PER-CENT PER-CENT 4054700800026
0.35 0.71 0.3 0.43 0.34 0.12 4054700800027
0.62 0.58 0.61 0.71 4054700800028
ENDCOMMON 6 0 4054700800029
DATA 3 1 4054700800030
KT DATA ERR-T 4054700800031
MEV MB MB 4054700800032
1.406 1861. 30. 4054700800033
ENDDATA 3 0 4054700800034
ENDSUBENT 33 0 4054700899999
SUBENT 40547009 20201109 41934054700900001
BIB 8 22 4054700900002
REACTION (94-PU-239(N,F),,SIG) 4054700900003
FACILITY (CCW) 4054700900004
INC-SOURCE (D-T) 4054700900005
METHOD (ASSOP) Detection of fission fragments and alpha 4054700900006
PART-DET (FF,A) 4054700900007
ERR-ANALYS (ERR-T) Total uncertainty (1.76%)4054700900008
(ERR-3) sample weight- solid angle of camera (0.3%)4054700900009
(ERR-4) sample weight- statistics (0.35%)4054700900010
(ERR-5) sample weight- isotopic fraction (0.34%)4054700900011
(ERR-6) sample weight- isotope half-life (0.12%)4054700900012
(ERR-7) fission- statistics (1.0%)4054700900013
(ERR-8) fission- random coincidence (0.2%)4054700900014
(ERR-9) fission- neutron flux loss (1.0%)4054700900015
(ERR-10) fission- extrapolation to 0-energy (0.36%)4054700900016
(ERR-11) fission- fragment absorption in a layer(0.30%)4054700900017
(ERR-12) fission- impurity fission (0.71%)4054700900018
(ERR-13) number of associated particle (0.05%)4054700900019
STATUS (TABLE) Tables 2 (error) +3 (data) of YK-24,8,1977 4054700900020
(SPSDD,40547017) improved finite geometry correction 4054700900021
HISTORY (20191213A) Code (SPSDD,22304009) was deleted - 4054700900022
in 22304 - different measurement in Germany. 4054700900023
(20201104A) On. Superseded. ERR-ANALYS revised. 4054700900024
ENDBIB 22 0 4054700900025
COMMON 11 6 4054700900026
ERR-3 ERR-4 ERR-5 ERR-6 ERR-7 ERR-8 4054700900027
ERR-9 ERR-10 ERR-11 ERR-12 ERR-13 4054700900028
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700900029
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054700900030
0.3 0.35 0.34 0.12 1.0 0.2 4054700900031
1.0 0.36 0.30 0.71 0.05 4054700900032
ENDCOMMON 6 0 4054700900033
DATA 3 1 4054700900034
EN DATA ERR-T 4054700900035
MEV MB MB 4054700900036
14.8 2620. 46. 4054700900037
ENDDATA 3 0 4054700900038
ENDSUBENT 37 0 4054700999999
SUBENT 40547010 20201109 41934054701000001
BIB 9 21 4054701000002
REACTION (92-U-233(N,F),,SIG,,FIS) 4054701000003
INC-SOURCE (CF252) 4054701000004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054701000005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments . 4054701000006
Time resolution of coincidence circuit 20 nsec. 4054701000007
CORRECTION For the solid angle 4054701000008
For neutron scattering (flux attenuation) 4054701000009
For nonuniformity of sample 4054701000010
For efficiency of detection 4054701000011
ANALYSIS Cross section was determined by formula: 4054701000012
SIGf=Nc/(Nf*NU*G*n), where 4054701000013
Nc - number of coincidences, 4054701000014
Nf - Cf-252 fission events, 4054701000015
NU - Cf-252 prompt neutron average number, 4054701000016
G - geometrical factor, 4054701000017
N - number of sample nuclei per 1 cm2. 4054701000018
ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 4054701000019
STATUS (TABLE) Table 2 of C,79KNOX,995,1979. 4054701000020
This Subent supersedes Subent 002. 4054701000021
HISTORY (20201104C) On 4054701000022
(20201109A) M.M. CORRECTION and ANALYSIS were added 4054701000023
ENDBIB 21 0 4054701000024
NOCOMMON 0 0 4054701000025
DATA 3 1 4054701000026
KT DATA DATA-ERR 4054701000027
MEV MB MB 4054701000028
1.406 1910. 29. 4054701000029
ENDDATA 3 0 4054701000030
ENDSUBENT 29 0 4054701099999
SUBENT 40547011 20201109 41934054701100001
BIB 10 22 4054701100002
REACTION (92-U-233(N,F),,SIG) 4054701100003
FACILITY (CCW) 4054701100004
INC-SOURCE (D-T) 4054701100005
METHOD (ASSOP) Detection of fission fragments and alpha 4054701100006
PART-DET (FF,A) 4054701100007
ANALYSIS Cross section was determined by formula: 4054701100008
SIGf=Nc/(Na*n), where 4054701100009
Nc - number of coincidences, 4054701100010
Na - number of associated alphas, 4054701100011
N - number of sample nuclei per 1 cm2. 4054701100012
CORRECTION For neutron flux attenuation ( <2% ), 4054701100013
for detection efficiency, 4054701100014
for random coincidences, 4054701100015
for nonuniformity of samples, 4054701100016
for finite geometry. 4054701100017
ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 4054701100018
STATUS (TABLE) Table 4 of C,79KNOX,995,1979 4054701100019
This Subent supersedes Subent 003. 4054701100020
HISTORY (20201104C) On 4054701100021
(20201109A) M.M. EN was corrected 14.8 -> 14.7+-0.2 MeV4054701100022
as given on page 996 of 79KNOX,995,1979. 4054701100023
CORRECTION and ANALYSIS were added. 4054701100024
ENDBIB 22 0 4054701100025
NOCOMMON 0 0 4054701100026
DATA 4 1 4054701100027
EN EN-ERR DATA DATA-ERR 4054701100028
MEV MEV B B 4054701100029
14.7 0.2 2.254 0.043 4054701100030
ENDDATA 3 0 4054701100031
ENDSUBENT 30 0 4054701199999
SUBENT 40547012 20201109 41934054701200001
BIB 9 21 4054701200002
REACTION (92-U-235(N,F),,SIG,,FIS) 4054701200003
INC-SOURCE (CF252) 4054701200004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054701200005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments 4054701200006
Time resolution of coincidence circuit 20 nsec. 4054701200007
CORRECTION For the solid angle 4054701200008
For neutron scattering (flux attenuation) 4054701200009
For nonuniformity of sample 4054701200010
For efficiency of detection 4054701200011
ANALYSIS Cross section was determined by formula: 4054701200012
SIGf=Nc/(Nf*NU*G*n), where 4054701200013
Nc - number of coincidences, 4054701200014
Nf - Cf-252 fission events, 4054701200015
NU - Cf-252 prompt neutron average number, 4054701200016
G - geometrical factor, 4054701200017
N - number of sample nuclei per 1 cm2. 4054701200018
ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 4054701200019
STATUS (TABLE) Table 2 of C,79KNOX,995,1979 4054701200020
This Subent supersedes Subent 004. 4054701200021
HISTORY (20201104C) On 4054701200022
(20201109A) M.M. CORRECTION and ANALYSIS were added 4054701200023
ENDBIB 21 0 4054701200024
NOCOMMON 0 0 4054701200025
DATA 3 1 4054701200026
KT DATA DATA-ERR 4054701200027
MEV MB MB 4054701200028
1.406 1241. 18. 4054701200029
ENDDATA 3 0 4054701200030
ENDSUBENT 29 0 4054701299999
SUBENT 40547013 20201109 41934054701300001
BIB 10 23 4054701300002
REACTION (92-U-235(N,F),,SIG) 4054701300003
FACILITY (CCW) 4054701300004
INC-SOURCE (D-T) 4054701300005
METHOD (ASSOP) Detection of fission fragments and alpha 4054701300006
PART-DET (FF,A) 4054701300007
ANALYSIS Cross section was determined by formula: 4054701300008
SIGf=Nc/(Na*n), where 4054701300009
Nc - number of coincidences, 4054701300010
Na - number of associated alphas, 4054701300011
N - number of sample nuclei per 1 cm2. 4054701300012
CORRECTION For neutron flux attenuation ( <2% ), 4054701300013
for detection efficiency, 4054701300014
for random coincidences, 4054701300015
for nonuniformity of samples, 4054701300016
for finite geometry. 4054701300017
ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 4054701300018
STATUS (TABLE) Table 5 of C,79KNOX,995,1979 4054701300019
This Subent supersedes Subent 005. 4054701300020
HISTORY (20201104C) On 4054701300021
(20201109A) M.M. EN was corrected 14.8 -> 14.7+-0.2 MeV4054701300022
as given on page 996 of 79KNOX,995,1979 4054701300023
CORRECTION and ANALYSIS were added. 4054701300024
Table 4 -> Table 5 in STATUS. 4054701300025
ENDBIB 23 0 4054701300026
NOCOMMON 0 0 4054701300027
DATA 4 1 4054701300028
EN EN-ERR DATA DATA-ERR 4054701300029
MEV MEV B B 4054701300030
14.7 0.2 2.089 0.040 4054701300031
ENDDATA 3 0 4054701300032
ENDSUBENT 31 0 4054701399999
SUBENT 40547014 20201109 41934054701400001
BIB 9 21 4054701400002
REACTION (92-U-238(N,F),,SIG,,FIS) 4054701400003
INC-SOURCE (CF252) 4054701400004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054701400005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments 4054701400006
Time resolution of coincidence circuit 20 nsec. 4054701400007
CORRECTION For the solid angle 4054701400008
For neutron scattering (flux attenuation) 4054701400009
For nonuniformity of sample 4054701400010
For efficiency of detection 4054701400011
ANALYSIS Cross section was determined by formula: 4054701400012
SIGf=Nc/(Nf*NU*G*n), where 4054701400013
Nc - number of coincidences, 4054701400014
Nf - Cf-252 fission events, 4054701400015
NU - Cf-252 prompt neutron average number, 4054701400016
G - geometrical factor, 4054701400017
N - number of sample nuclei per 1 cm2. 4054701400018
ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 4054701400019
STATUS (TABLE) Table 2 of C,79KNOX,995,1979 4054701400020
This Subent supersedes Subent 006. 4054701400021
HISTORY (20201104C) On 4054701400022
(20201109A) M.M. CORRECTION and ANALYSIS were added 4054701400023
ENDBIB 21 0 4054701400024
NOCOMMON 0 0 4054701400025
DATA 3 1 4054701400026
KT DATA DATA-ERR 4054701400027
MEV MB MB 4054701400028
1.406 344. 6. 4054701400029
ENDDATA 3 0 4054701400030
ENDSUBENT 29 0 4054701499999
SUBENT 40547015 20201109 41934054701500001
BIB 10 22 4054701500002
REACTION (92-U-238(N,F),,SIG) 4054701500003
FACILITY (CCW) 4054701500004
INC-SOURCE (D-T) 4054701500005
METHOD (ASSOP) Detection of fission fragments and alpha 4054701500006
PART-DET (FF,A) 4054701500007
ANALYSIS Cross section was determined by formula: 4054701500008
SIGf=Nc/(Na*n), where 4054701500009
Nc - number of coincidences, 4054701500010
Na - number of associated alphas, 4054701500011
N - number of sample nuclei per 1 cm2. 4054701500012
CORRECTION For neutron flux attenuation ( <2% ), 4054701500013
for detection efficiency, 4054701500014
for random coincidence9, 4054701500015
for nonuniformity of samples, 4054701500016
for finite geometry. 4054701500017
ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 4054701500018
STATUS (TABLE) Table 4 of C,79KNOX,995,1979 4054701500019
This Subent superseds Subent 007. 4054701500020
HISTORY (20201104C) On 4054701500021
(20201109A) M.M. EN was corrected 14.8 -> 14.7+-0.2 MeV4054701500022
as given on page 996 of 79KNOX,995,1979 4054701500023
CORRECTION and ANALYSIS were added. 4054701500024
ENDBIB 22 0 4054701500025
NOCOMMON 0 0 4054701500026
DATA 4 1 4054701500027
EN EN-ERR DATA DATA-ERR 4054701500028
MEV MEV B B 4054701500029
14.7 0.2 1.178 0.024 4054701500030
ENDDATA 3 0 4054701500031
ENDSUBENT 30 0 4054701599999
SUBENT 40547016 20201109 41934054701600001
BIB 9 21 4054701600002
REACTION (94-PU-239(N,F),,SIG,,FIS) 4054701600003
INC-SOURCE (CF252) 4054701600004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054701600005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments 4054701600006
Time resolution of coincidence circuit 20 nsec. 4054701600007
CORRECTION For the solid angle 4054701600008
For neutron scattering (flux attenuation) 4054701600009
For nonuniformity of sample 4054701600010
For efficiency of detection 4054701600011
ANALYSIS Cross section was determined by formula: 4054701600012
SIGf=Nc/(Nf*NU*G*n), where 4054701600013
Nc - number of coincidences, 4054701600014
Nf - Cf-252 fission events, 4054701600015
NU - Cf-252 prompt neutron average number, 4054701600016
G - geometrical factor, 4054701600017
N - number of sample nuclei per 1 cm2. 4054701600018
ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 4054701600019
STATUS (TABLE) Table 2 of C,79KNOX,995,1979 4054701600020
This Subent supersedes Subent 008. 4054701600021
HISTORY (20201104C) On 4054701600022
(20201109A) M.M. CORRECTION and ANALYSIS were added 4054701600023
ENDBIB 21 0 4054701600024
NOCOMMON 0 0 4054701600025
DATA 3 1 4054701600026
KT DATA DATA-ERR 4054701600027
MEV MB MB 4054701600028
1.406 1831. 27. 4054701600029
ENDDATA 3 0 4054701600030
ENDSUBENT 29 0 4054701699999
SUBENT 40547017 20210623 41964054701700001
BIB 10 23 4054701700002
REACTION (94-PU-239(N,F),,SIG) 4054701700003
FACILITY (CCW) 4054701700004
INC-SOURCE (D-T) 4054701700005
METHOD (ASSOP) Detection of fission fragments and alpha 4054701700006
PART-DET (FF,A) 4054701700007
ANALYSIS Cross section was determined by formula: 4054701700008
SIGf=Nc/(Na*n), where 4054701700009
Nc - number of coincidences, 4054701700010
Na - number of associated alphas, 4054701700011
N - number of sample nuclei per 1 cm2. 4054701700012
CORRECTION For neutron flux attenuation ( <2% ), 4054701700013
for detection efficiency, 4054701700014
for random coincidences, 4054701700015
for nonuniformity of samples, 4054701700016
for finite geometry. 4054701700017
ERR-ANALYS (DATA-ERR) No information on the source of uncertainty 4054701700018
STATUS (TABLE) Table 4 of C,79KNOX,995,1979 4054701700019
This Subent supersedes Subent 009. 4054701700020
HISTORY (20201104C) On 4054701700021
(20201109A) M.M. EN was corrected 14.8 -> 14.7+-0.2 MeV4054701700022
as given on page 996 of 79KNOX,995,1979 4054701700023
CORRECTION and ANALYSIS were added. 4054701700024
(20210623A) On. MB -> B. 4054701700025
ENDBIB 23 0 4054701700026
NOCOMMON 0 0 4054701700027
DATA 4 1 4054701700028
EN EN-ERR DATA DATA-ERR 4054701700029
MEV MEV B B 4054701700030
14.7 0.2 2.505 0.051 4054701700031
ENDDATA 3 0 4054701700032
ENDSUBENT 31 0 4054701799999
SUBENT 40547018 20201109 41934054701800001
BIB 10 30 4054701800002
REACTION (92-U-234(N,F),,SIG,,FIS) 4054701800003
INC-SOURCE (CF252) 4054701800004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054701800005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments . 4054701800006
Time resolution of coincidence circuit 20 nsec. 4054701800007
DECAY-DATA (92-U-234,2.488E+5YR) (2.488+-0.016)*10**5 yr 4054701800008
CORRECTION For the solid angle 4054701800009
For neutron scattering (flux attenuation) 4054701800010
For nonuniformity of sample 4054701800011
For efficiency of detection 4054701800012
For fragment absorption 4054701800013
ANALYSIS Cross section was determined by formula: 4054701800014
SIGf=Nc/(Nf*NU*G*n), where 4054701800015
Nc - number of coincidences, 4054701800016
Nf - Cf-252 fission events, 4054701800017
NU - Cf-252 prompt neutron average number, 4054701800018
G - geometrical factor, 4054701800019
N - number of sample nuclei per 1 cm2. 4054701800020
ERR-ANALYS (ERR-T) Total uncertainty (4.65%) 4054701800021
Sources of uncertainties: 4054701800022
(ERR-1) NU of Cf-252 4054701800023
(ERR-2) Geometrical factor 4054701800024
(ERR-3) Measurement of alpha-activity 4054701800025
(ERR-4) Coincidence statistics 4054701800026
(ERR-5) Extrapolation to fragment zero pulse-height 4054701800027
(ERR-6) Correction for fragment absorption 4054701800028
(ERR-7) Half-life 4054701800029
STATUS (TABLE) Table 2 (data), Table 1 (uncertainties) 4054701800030
of C,79KNOX,995,1979. 4054701800031
HISTORY (20201109C) M.M. 4054701800032
ENDBIB 30 0 4054701800033
COMMON 6 3 4054701800034
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4054701800035
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054701800036
0.35 0.71 0.36 4.5 0.30 0.30 4054701800037
ENDCOMMON 3 0 4054701800038
DATA 4 1 4054701800039
KT-DUMMY DATA ERR-T ERR-7 4054701800040
MEV MB MB PER-CENT 4054701800041
1.406 1220. 60. 0.64 4054701800042
ENDDATA 3 0 4054701800043
ENDSUBENT 42 0 4054701899999
SUBENT 40547019 20201109 41934054701900001
BIB 10 30 4054701900002
REACTION (92-U-236(N,F),,SIG,,FIS) 4054701900003
INC-SOURCE (CF252) 4054701900004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054701900005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments . 4054701900006
Time resolution of coincidence circuit 20 nsec. 4054701900007
DECAY-DATA (92-U-236,2.391E+7YR) (2.391+-0.018)*10**7 yr 4054701900008
CORRECTION For the solid angle 4054701900009
For neutron scattering (flux attenuation) 4054701900010
For nonuniformity of sample 4054701900011
For efficiency of detection 4054701900012
For fragment absorption 4054701900013
ANALYSIS Cross section was determined by formula: 4054701900014
SIGf=Nc/(Nf*NU*G*n), where 4054701900015
Nc - number of coincidences, 4054701900016
Nf - Cf-252 fission events, 4054701900017
NU - Cf-252 prompt neutron average number, 4054701900018
G - geometrical factor, 4054701900019
N - number of sample nuclei per 1 cm2. 4054701900020
ERR-ANALYS (ERR-T) Total uncertainty (4.78%) 4054701900021
Sources of uncertainties: 4054701900022
(ERR-1) NU of Cf-252 4054701900023
(ERR-2) Geometrical factor 4054701900024
(ERR-3) Measurement of alpha-activity 4054701900025
(ERR-4) Coincidence statistics 4054701900026
(ERR-5) Extrapolation to fragment zero pulse-height 4054701900027
(ERR-6) Correction for fragment absorption 4054701900028
(ERR-7) Half-life 4054701900029
STATUS (TABLE) Table 2 (data), Table 1 (uncertainties) 4054701900030
of C,79KNOX,995,1979. 4054701900031
HISTORY (20201109C) M.M. 4054701900032
ENDBIB 30 0 4054701900033
COMMON 6 3 4054701900034
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4054701900035
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054701900036
0.35 0.71 1.04 4.5 0.45 0.30 4054701900037
ENDCOMMON 3 0 4054701900038
DATA 4 1 4054701900039
KT-DUMMY DATA ERR-T ERR-7 4054701900040
MEV MB MB PER-CENT 4054701900041
1.406 610. 30. 0.80 4054701900042
ENDDATA 3 0 4054701900043
ENDSUBENT 42 0 4054701999999
SUBENT 40547020 20201109 41934054702000001
BIB 10 22 4054702000002
REACTION (94-PU-242(N,F),,SIG,,FIS) 4054702000003
INC-SOURCE (CF252) 4054702000004
INC-SPECT 252Cf(sf) fission neutron spectrum 4054702000005
METHOD (ASSOP) Detection of (n,f) and 252Cf(sf) fragments . 4054702000006
Time resolution of coincidence circuit 20 nsec. 4054702000007
DECAY-DATA (92-U-234,2.488E+5YR) (2.488+-0.016)*10**5 hr 4054702000008
CORRECTION For the solid angle 4054702000009
For neutron scattering (flux attenuation) 4054702000010
For nonuniformity of sample 4054702000011
For efficiency of detection 4054702000012
For fragment absorption 4054702000013
ANALYSIS Cross section was determined by formula: 4054702000014
SIGf=Nc/(Nf*NU*G*n), where 4054702000015
Nc - number of coincidences, 4054702000016
Nf - Cf-252 fission events, 4054702000017
NU - Cf-252 prompt neutron average number, 4054702000018
G - geometrical factor, 4054702000019
N - number of sample nuclei per 1 cm2. 4054702000020
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained 4054702000021
in the article. 4054702000022
STATUS (TABLE) Table 2 of C,79KNOX,995,1979. 4054702000023
HISTORY (20201109C) M.M. 4054702000024
ENDBIB 22 0 4054702000025
NOCOMMON 0 0 4054702000026
DATA 3 1 4054702000027
KT-DUMMY DATA DATA-ERR 4054702000028
MEV MB MB 4054702000029
1.406 1092. 18. 4054702000030
ENDDATA 3 0 4054702000031
ENDSUBENT 30 0 4054702099999
SUBENT 40547021 20201109 41934054702100001
BIB 11 29 4054702100002
REACTION (92-U-234(N,F),,SIG) 4054702100003
FACILITY (CCW) 4054702100004
INC-SOURCE (D-T) 4054702100005
METHOD (ASSOP) Detection of fission fragments and alpha 4054702100006
PART-DET (FF,A) 4054702100007
DECAY-DATA (92-U-234,2.488E+5YR) (2.488+-0.016)*10**5 yr 4054702100008
ANALYSIS Cross section was determined by formula: 4054702100009
SIGf=Nc/(Na*n), where 4054702100010
Nc - number of coincidences, 4054702100011
Na - number of associated alphas, 4054702100012
N - number of sample nuclei per 1 cm2. 4054702100013
CORRECTION For neutron flux attenuation ( <2% ), 4054702100014
for detection efficiency, 4054702100015
for random coincidences, 4054702100016
for nonuniformity of samples, 4054702100017
for finite geometry. 4054702100018
ERR-ANALYS (ERR-T) Total uncertainty 4054702100019
Sources of uncertainties: 4054702100020
(ERR-1) Measurement of alpha-activity 4054702100021
(ERR-2) Half-life 4054702100022
(ERR-3) Coincidence statistics 4054702100023
(ERR-4) Neutron flux attenuation 4054702100024
(ERR-5) Extrapolation to fragment zero pulse-height 4054702100025
(ERR-6) Correction for fragment absorption 4054702100026
(ERR-7) Nonuniformity of sample 4054702100027
(ERR-8) Background in associated particles 4054702100028
STATUS (TABLE) Table 4 (data), Table 3 (uncertainties) 4054702100029
of C,79KNOX,995,1979 4054702100030
HISTORY (20201109C) M.M. 4054702100031
ENDBIB 29 0 4054702100032
COMMON 6 3 4054702100033
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4054702100034
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054702100035
0.36 0.64 1.00 0.30 0.20 0.20 4054702100036
ENDCOMMON 3 0 4054702100037
DATA 6 1 4054702100038
EN EN-ERR DATA ERR-T ERR-7 ERR-8 4054702100039
MEV MEV B B PER-CENT PER-CENT 4054702100040
14.7 0.2 1.91 0.11 5.00 0.05 4054702100041
ENDDATA 3 0 4054702100042
ENDSUBENT 41 0 4054702199999
SUBENT 40547022 20201109 41934054702200001
BIB 11 29 4054702200002
REACTION (92-U-236(N,F),,SIG) 4054702200003
FACILITY (CCW) 4054702200004
INC-SOURCE (D-T) 4054702200005
METHOD (ASSOP) Detection of fission fragments and alpha 4054702200006
PART-DET (FF,A) 4054702200007
DECAY-DATA (92-U-236,2.391E+7YR) (2.391+-0.018)*10**7 yr 4054702200008
ANALYSIS Cross section was determined by formula: 4054702200009
SIGf=Nc/(Na*n), where 4054702200010
Nc - number of coincidences, 4054702200011
Na - number of associated alphas, 4054702200012
N - number of sample nuclei per 1 cm2. 4054702200013
CORRECTION For neutron flux attenuation ( <2% ), 4054702200014
for detection efficiency, 4054702200015
for random coincidences, 4054702200016
for nonuniformity of samples, 4054702200017
for finite geometry. 4054702200018
ERR-ANALYS (ERR-T) Total uncertainty 4054702200019
Sources of uncertainties: 4054702200020
(ERR-1) Measurement of alpha-activity 4054702200021
(ERR-2) Half-life 4054702200022
(ERR-3) Coincidence statistics 4054702200023
(ERR-4) Neutron flux attenuation 4054702200024
(ERR-5) Extrapolation to fragment zero pulse-height 4054702200025
(ERR-6) Correction for fragment absorption 4054702200026
(ERR-7) Nonuniformity of sample 4054702200027
(ERR-8) Background in associated particles 4054702200028
STATUS (TABLE) Table 4 (data), Table 3 (uncertainties) 4054702200029
of C,79KNOX,995,1979 4054702200030
HISTORY (20201109C) M.M. 4054702200031
ENDBIB 29 0 4054702200032
COMMON 6 3 4054702200033
ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 4054702200034
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 4054702200035
1.04 0.80 1.00 0.30 0.20 0.20 4054702200036
ENDCOMMON 3 0 4054702200037
DATA 6 1 4054702200038
EN EN-ERR DATA ERR-T ERR-7 ERR-8 4054702200039
MEV MEV B B PER-CENT PER-CENT 4054702200040
14.7 0.2 1.62 0.08 4.50 0.05 4054702200041
ENDDATA 3 0 4054702200042
ENDSUBENT 41 0 4054702299999
SUBENT 40547023 20201109 41934054702300001
BIB 10 30 4054702300002
REACTION (92-U-235(N,F),,SIG) 4054702300003
FACILITY (CCW) 4054702300004
INC-SOURCE (D-T) 14.0 and 14.5 MeV neutrons were obtained by 4054702300005
choice of angle between the deuteron beam and neutron 4054702300006
cone axis as 45 and 90 deg. 4054702300007
METHOD (ASSOP) Detection of fission fragments and alpha 4054702300008
PART-DET (FF,A) 4054702300009
ANALYSIS Cross section was determined by formula: 4054702300010
SIGf=Nc/(Na*n), where 4054702300011
Nc - number of coincidences, 4054702300012
Na - number of associated alphas, 4054702300013
N - number of sample nuclei per 1 cm2. 4054702300014
CORRECTION For neutron flux attenuation ( <2% ), 4054702300015
for detection efficiency, 4054702300016
for random coincidences, 4054702300017
for nonuniformity of samples, 4054702300018
for finite geometry. 4054702300019
ERR-ANALYS (ERR-T) Total uncertainty 4054702300020
Sources of uncertainties,% at 14.7 MeV: 4054702300021
Measurement of alpha-activity 0.62 4054702300022
Coincidence statistics 0.70 4054702300023
Neutron flux attenuation 0.30 4054702300024
Extrapolation to fragment zero pulse-height 0.20 4054702300025
Correction for fragment absorption 0.30 4054702300026
Nonuniformity of sample 1.00 4054702300027
Background in associated particles 0.05 4054702300028
(ERR-1) Half-life 0.20 4054702300029
STATUS (TABLE) Table 5 (data), Table 3 (uncertainties) 4054702300030
of C,79KNOX,995,1979 4054702300031
HISTORY (20201109C) M.M. 4054702300032
ENDBIB 30 0 4054702300033
COMMON 1 3 4054702300034
ERR-1 4054702300035
PER-CENT 4054702300036
0.20 4054702300037
ENDCOMMON 3 0 4054702300038
DATA 4 3 4054702300039
EN EN-ERR DATA ERR-T 4054702300040
MEV MEV B B 4054702300041
14.7 0.2 2.096 0.031 4054702300042
14.5 2.101 0.034 4054702300043
14.0 2.084 0.034 4054702300044
ENDDATA 5 0 4054702300045
ENDSUBENT 44 0 4054702399999
SUBENT 40547024 20201109 41934054702400001
BIB 10 18 4054702400002
REACTION (94-PU-242(N,F),,SIG) 4054702400003
FACILITY (CCW) 4054702400004
INC-SOURCE (D-T) 4054702400005
METHOD (ASSOP) Detection of fission fragments and alpha 4054702400006
PART-DET (FF,A) 4054702400007
ANALYSIS Cross section was determined by formula: 4054702400008
SIGf=Nc/(Na*n), where 4054702400009
Nc - number of coincidences, 4054702400010
Na - number of associated alphas, 4054702400011
N - number of sample nuclei per 1 cm2. 4054702400012
CORRECTION For neutron flux attenuation ( <2% ), 4054702400013
for detection efficiency, 4054702400014
for random coincidences, 4054702400015
for nonuniformity of samples, 4054702400016
for finite geometry. 4054702400017
ERR-ANALYS (DATA-ERR) Type of uncertainty is not explained in 4054702400018
STATUS (TABLE) Table 4 of C,79KNOX,995,1979 4054702400019
HISTORY (20201109C) M.M. 4054702400020
ENDBIB 18 0 4054702400021
NOCOMMON 0 0 4054702400022
DATA 4 1 4054702400023
EN EN-ERR DATA DATA-ERR 4054702400024
MEV MEV B B 4054702400025
14.7 0.2 2.050 0.040 4054702400026
ENDDATA 3 0 4054702400027
ENDSUBENT 26 0 4054702499999
ENDENTRY 24 0 4054799999999