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