ENTRY 40806 20130803 41614080600000001 SUBENT 40806001 20130803 41614080600100001 BIB 12 34 4080600100002 AUTHOR (N.N.Flerov,V.M.Talyzin) 4080600100003 TITLE NU, mean number of neutrons emitted in fission 4080600100004 of U-235 and U-238 by 14 MeV neutrons. 4080600100005 INSTITUTE (4RUSKUR) 4080600100006 REFERENCE (J,AE,5,(6),653,1958) Main Reference. Data Table. 4080600100007 (J,SJA,5,1593,1958) Engl.transl. of AE,5,(6),653,1958 .4080600100008 (J,JNE/A,11,169,1960) Engl.translation of AE,5,653,19584080600100009 REL-REF (I,,N.N.Flerov+,J,AE,3,201,1957) Exp. details 4080600100010 (I,,N.N.Flerov+,J,SJA,3,1095,1957) 4080600100011 Engl.transl. of AE,3,201,1957. 4080600100012 EXP-YEAR (1954) 4080600100013 SAMPLE Spherical samples of metallic U of external diameter 4080600100014 4cm, internal diameter 3.4 cm, aperture diameter 2.1cm,4080600100015 were covered by Cd of 0.9mm thick and placed in 4080600100016 a thin-walled brass container. 4080600100017 Natural and enriched 90.1% U-235 samples. 4080600100018 METHOD (SHELT) Spherical shell transmission 4080600100019 Ratio of detector sensitivities to 14 MeV neutrons and4080600100020 to neutrons from nonelastic processes - 0.874+-0.030. 4080600100021 DETECTOR (BF3) BF3 counter in graphite prism. 4080600100022 CORRECTION Inelastic scattering and (n,3n) reactions were 4080600100023 neglected. 4080600100024 ERR-ANALYS (DATA-ERR) Not explained. 4080600100025 HISTORY (19840904T) Converted from Entry 80263 4080600100026 (19970622A) * * Corrected numerical error in SAN 004 4080600100027 Corrected Institute code in SAN 001 4080600100028 Energy moved to SAN 001 4080600100029 (20000125U) . . Corrected at CJD 4080600100030 (20000125U) Last checking has been done. 4080600100031 (20050827U) Correction according to Memo CP-E/70 4080600100032 (20130803A) M.M. Engl.translations were added. 4080600100033 ABS -> NON in Subents 002,004 according to memo 4080600100034 CP-D/798 (N.Otsuka, NDS,IAEA) . 4080600100035 BIB information was updated. 4080600100036 ENDBIB 34 0 4080600100037 COMMON 1 3 4080600100038 EN 4080600100039 MEV 4080600100040 1.4E+01 4080600100041 ENDCOMMON 3 0 4080600100042 ENDSUBENT 41 0 4080600199999 SUBENT 40806002 20130803 41614080600200001 BIB 7 11 4080600200002 REACTION (92-U-235(N,NON),,ETA) 4080600200003 MONITOR (92-U-235(N,NON),,SIG) 4080600200004 MISC-COL (MISC1) Coefficient taking into account increasing 4080600200005 number of neutrons due to fission induced by secondary 4080600200006 neutrons.Determined experimentally. 4080600200007 (MISC2) Coefficient taking into account fission induced4080600200008 by slow neutrons. Determined experimentally. 4080600200009 ASSUMED (ASSUM,92-U-235(N,F),,SIG) From: 4080600200010 REL-REF (R,,A.A.Berezin+,J,AE,5,659,1958) 4080600200011 STATUS (TABLE) Table of J,AE,5,(6),653,1958 4080600200012 HISTORY (19970622U) Neutron energy moved to Subent 001 4080600200013 ENDBIB 11 0 4080600200014 COMMON 4 3 4080600200015 MONIT MONIT-ERR ASSUM ASSUM-ERR 4080600200016 B B B B 4080600200017 2.85 0.10 2.30 0.15 4080600200018 ENDCOMMON 3 0 4080600200019 DATA 6 1 4080600200020 DATA DATA-ERR MISC1 MISC1-ERR MISC2 MISC2-ERR 4080600200021 PRT/REAC PRT/REAC NO-DIM NO-DIM NO-DIM NO-DIM 4080600200022 3.71 2.E-01 1.062 0.008 1.002 0.003 4080600200023 ENDDATA 3 0 4080600200024 ENDSUBENT 23 0 4080600299999 SUBENT 40806003 20130803 41614080600300001 BIB 4 5 4080600300002 REACTION (92-U-235(N,F),PR,NU) 4080600300003 ERR-ANALYS (ERR-1,2.,5.) Error due to neglected reactions - 4080600300004 inelastic and n,3n. 4080600300005 STATUS (TABLE) Table of J,AE,5,(6),653,1958 4080600300006 HISTORY (19970622U) Neutron energy moved to Subent 001 4080600300007 ENDBIB 5 0 4080600300008 NOCOMMON 0 0 4080600300009 DATA 2 1 4080600300010 DATA DATA-ERR 4080600300011 PRT/FIS PRT/FIS 4080600300012 4.13 2.4E-01 4080600300013 ENDDATA 3 0 4080600300014 ENDSUBENT 13 0 4080600399999 SUBENT 40806004 20130803 41614080600400001 BIB 7 13 4080600400002 REACTION (92-U-238(N,NON),,ETA) 4080600400003 MONITOR (92-U-238(N,NON),,SIG) 4080600400004 MISC-COL (MISC1) Coefficient taking into account increasing 4080600400005 number of neutrons due to fission induced by secondary 4080600400006 neutrons.Computed under assumption that fission c-s is 4080600400007 0.27+-0.03 b. 4080600400008 (MISC2) Coefficient taking into account fission induced4080600400009 by slow neutrons was 1. 4080600400010 ASSUMED (ASSUM,92-U-238(N,F),,SIG) From: 4080600400011 REL-REF (R,,N.N.Flerov+,J,AE,5,657,1958) 4080600400012 STATUS (TABLE) Table of J,AE,5,(6),653,1958 4080600400013 HISTORY (19970622A)Corrected numerical error in U-238 ETA value4080600400014 Neutron energy moved to Subent 001 4080600400015 ENDBIB 13 0 4080600400016 COMMON 4 3 4080600400017 ASSUM ASSUM-ERR MONIT MONIT-ERR 4080600400018 B B B B 4080600400019 1.13 0.05 2.85 0.10 4080600400020 ENDCOMMON 3 0 4080600400021 DATA 5 1 4080600400022 DATA DATA-ERR MISC1 MISC1-ERR MISC2 4080600400023 PRT/REAC PRT/REAC NO-DIM NO-DIM NO-DIM 4080600400024 2.99 1.5E-01 1.011 0.001 1. 4080600400025 ENDDATA 3 0 4080600400026 ENDSUBENT 25 0 4080600499999 SUBENT 40806005 20130803 41614080600500001 BIB 4 6 4080600500002 REACTION (92-U-238(N,F),PR,NU) 4080600500003 ERR-ANALYS (ERR-1,2.,5.) Error due to neglected reactions - 4080600500004 inelastic and n,3n. 4080600500005 STATUS (TABLE) Table of J,AE,5,(6),653,1958 4080600500006 (COREL,41254002) Different measurement 4080600500007 HISTORY (19970622U) Neutron energy moved to Subent 001 4080600500008 ENDBIB 6 0 4080600500009 NOCOMMON 0 0 4080600500010 DATA 2 1 4080600500011 DATA DATA-ERR 4080600500012 PRT/FIS PRT/FIS 4080600500013 4.5 3.2E-01 4080600500014 ENDDATA 3 0 4080600500015 ENDSUBENT 14 0 4080600599999 ENDENTRY 5 0 4080699999999