ENTRY 14195 20160315 14161419500000001 SUBENT 14195001 20160315 14161419500100001 BIB 10 24 1419500100002 TITLE Prompt gamma rays from 235U(n,f), 239Pu(n,f) and 1419500100003 spontaneous fission of 252Cf 1419500100004 AUTHOR (V.V.Verbinski,H.Weber,R.E.Sund) 1419500100005 INSTITUTE (1USAIRT) 1419500100006 REFERENCE (J,PR/C,7,1173,1973) 1419500100007 FACILITY (REAC,1USAIRT) 1419500100008 SAMPLE Thin sample of fissionable material placed 1419500100009 close to fission fragment detector 1419500100010 DETECTOR (NAICR,SIBAR)NaI crystal surrounded by NaI anti- 1419500100011 Compton shield placed at a distance of 70 cm from 1419500100012 sample used for gamma ray detection.Surface barrier 1419500100013 detector was used for fission fragment detection 1419500100014 METHOD (TOF,FPGAM) Time-of flight used for elimination 1419500100015 of prompt fission neutrons. Surface barrier 1419500100016 detector provided time reference for fission 1419500100017 events. Time resolution was better than 4 ns 1419500100018 ERR-ANALYS (ERR-1,,3.) Upper limit of uncertainty in 1419500100019 detection efficiency, not included in table 1419500100020 HISTORY (20081110C) Compiled by S.H. 1419500100021 (20120809A) SD: EN moved from Subent 1 to Subents 2,3. 1419500100022 REACTION code in Subents 2,3 was corrected according 1419500100023 to new EXFOR rules. 1419500100024 (20160315A) OS. Data point in sub.2 corrected, 1419500100025 subs. 5-7 added 1419500100026 ENDBIB 24 0 1419500100027 NOCOMMON 0 0 1419500100028 ENDSUBENT 27 0 1419500199999 SUBENT 14195002 20160315 14161419500200001 BIB 4 8 1419500200002 REACTION (92-U-235(N,F)0-G-0,PR/PAR,FY) 1419500200003 STATUS (TABLE) Data taken from Tab.1 of PR/C,7,1173,1973 1419500200004 INC-SOURCE (THCOL) Samples irradiated by thermal neutron 1419500200005 beam 1419500200006 HISTORY (20120809A) SD REACTION code corrected according to 1419500200007 new EXFOR rules (MLT,G => FY + SF4=G-0); units in 1419500200008 col. DATA changed (PRT/FIS => PRD/FIS) 1419500200009 (20160315A) Data point at 2.0/2.5 MeV corrected 1419500200010 ENDBIB 8 0 1419500200011 COMMON 1 3 1419500200012 EN 1419500200013 EV 1419500200014 0.0253 1419500200015 ENDCOMMON 3 0 1419500200016 DATA 3 13 1419500200017 E-MIN E-MAX DATA 1419500200018 MEV MEV PRD/FIS 1419500200019 0.14 0.3 0.833 1419500200020 0.3 0.5 1.318 1419500200021 0.5 0.7 1.182 1419500200022 0.7 1.0 1.191 1419500200023 1.0 1.5 1.072 1419500200024 1.5 2.0 0.461 1419500200025 2.0 2.5 0.258 1419500200026 2.5 3.0 0.158 1419500200027 3.0 4.0 0.143 1419500200028 4.0 5.0 0.050 1419500200029 5.0 6.0 0.021 1419500200030 6.0 7.0 0.0098 1419500200031 7.0 10.0 0.0027 1419500200032 ENDDATA 15 0 1419500200033 ENDSUBENT 32 0 1419500299999 SUBENT 14195003 20120809 13851419500300001 BIB 4 7 1419500300002 REACTION (94-PU-239(N,F)0-G-0,PR/PAR,FY) 1419500300003 STATUS (TABLE) data taken from Tab.1 of PR/C,7,1173,1973 1419500300004 INC-SOURCE (THCOL) Samples irradiated by thermal neutron 1419500300005 beam 1419500300006 HISTORY (20120809A) SD REACTION code corrected according to 1419500300007 new EXFOR rules (MLT,G => FY + SF4=G-0); units in 1419500300008 col. DATA changed (PRT/FIS => PRD/FIS) 1419500300009 ENDBIB 7 0 1419500300010 COMMON 1 3 1419500300011 EN 1419500300012 EV 1419500300013 0.0253 1419500300014 ENDCOMMON 3 0 1419500300015 DATA 3 13 1419500300016 E-MIN E-MAX DATA 1419500300017 MEV MEV PRD/FIS 1419500300018 0.14 0.3 1.267 1419500300019 0.3 0.5 1.473 1419500300020 0.5 0.7 1.219 1419500300021 0.7 1.0 1.097 1419500300022 1.0 1.5 0.998 1419500300023 1.5 2.0 0.450 1419500300024 2.0 2.5 0.268 1419500300025 2.5 3.0 0.175 1419500300026 3.0 4.0 0.173 1419500300027 4.0 5.0 0.0714 1419500300028 5.0 6.0 0.0265 1419500300029 6.0 7.0 0.0104 1419500300030 7.0 10.0 0.0015 1419500300031 ENDDATA 15 0 1419500300032 ENDSUBENT 31 0 1419500399999 SUBENT 14195004 20081110 13511419500400001 BIB 2 2 1419500400002 REACTION (98-CF-252(0,F),PR/PAR,MLT,G) 1419500400003 STATUS (TABLE) data taken from Tab.1 of the reference 1419500400004 ENDBIB 2 0 1419500400005 NOCOMMON 0 0 1419500400006 DATA 3 13 1419500400007 E-MIN E-MAX DATA 1419500400008 MEV MEV PRT/FIS 1419500400009 0.14 0.3 1.270 1419500400010 0.3 0.5 1.855 1419500400011 0.5 0.7 1.613 1419500400012 0.7 1.0 1.067 1419500400013 1.0 1.5 0.838 1419500400014 1.5 2.0 0.442 1419500400015 2.0 2.5 0.292 1419500400016 2.5 3.0 0.183 1419500400017 3.0 4.0 0.160 1419500400018 4.0 5.0 0.058 1419500400019 5.0 6.0 0.019 1419500400020 6.0 7.0 0.0057 1419500400021 7.0 10.0 0.0004 1419500400022 ENDDATA 15 0 1419500400023 ENDSUBENT 22 0 1419500499999 SUBENT 14195005 20160315 14161419500500001 BIB 5 6 1419500500002 REACTION (92-U-235(N,F)0-G-0,PR/PAR,KE) 1419500500003 STATUS (TABLE) Data taken from Tab.1 of PR/C,7,1173,1973 1419500500004 INC-SOURCE (THCOL) Samples irradiated by thermal neutron 1419500500005 beam 1419500500006 ERR-ANALYS (DATA-ERR) No details on sources of error given 1419500500007 HISTORY (20160315C) 1419500500008 ENDBIB 6 0 1419500500009 COMMON 1 3 1419500500010 EN 1419500500011 EV 1419500500012 0.0253 1419500500013 ENDCOMMON 3 0 1419500500014 DATA 4 13 1419500500015 E-MIN E-MAX DATA DATA-ERR 1419500500016 MEV MEV MEV MEV 1419500500017 0.14 0.3 0.181 0.005 1419500500018 0.3 0.5 0.532 0.013 1419500500019 0.5 0.7 0.709 0.028 1419500500020 0.7 1.0 1.021 0.026 1419500500021 1.0 1.5 1.337 0.034 1419500500022 1.5 2.0 0.804 0.020 1419500500023 2.0 2.5 0.582 0.015 1419500500024 2.5 3.0 0.434 0.012 1419500500025 3.0 4.0 0.490 0.015 1419500500026 4.0 5.0 0.220 0.015 1419500500027 5.0 6.0 0.116 0.011 1419500500028 6.0 7.0 0.0064 0.015 1419500500029 7.0 10.0 0.0019 0.015 1419500500030 ENDDATA 15 0 1419500500031 ENDSUBENT 30 0 1419500599999 SUBENT 14195006 20160315 14161419500600001 BIB 5 6 1419500600002 REACTION (94-PU-239(N,F)0-G-0,PR/PAR,KE) 1419500600003 STATUS (TABLE) Data taken from Tab.1 of PR/C,7,1173,1973 1419500600004 INC-SOURCE (THCOL) Samples irradiated by thermal neutron 1419500600005 beam 1419500600006 ERR-ANALYS (DATA-ERR) No details on sources of error given 1419500600007 HISTORY (20160315C) 1419500600008 ENDBIB 6 0 1419500600009 COMMON 1 3 1419500600010 EN 1419500600011 EV 1419500600012 0.0253 1419500600013 ENDCOMMON 3 0 1419500600014 DATA 4 13 1419500600015 E-MIN E-MAX DATA DATA-ERR 1419500600016 MEV MEV MEV MEV 1419500600017 0.14 0.3 0.275 0.007 1419500600018 0.3 0.5 0.596 0.015 1419500600019 0.5 0.7 0.737 0.019 1419500600020 0.7 1.0 0.939 0.023 1419500600021 1.0 1.5 1.241 0.031 1419500600022 1.5 2.0 0.787 0.020 1419500600023 2.0 2.5 0.606 0.015 1419500600024 2.5 3.0 0.482 0.014 1419500600025 3.0 4.0 0.597 0.017 1419500600026 4.0 5.0 0.318 0.019 1419500600027 5.0 6.0 0.145 0.018 1419500600028 6.0 7.0 0.067 0.012 1419500600029 7.0 10.0 0.019 0.012 1419500600030 ENDDATA 15 0 1419500600031 ENDSUBENT 30 0 1419500699999 SUBENT 14195007 20160315 14161419500700001 BIB 4 4 1419500700002 REACTION (98-CF-252(0,F)0-G-0,PR/PAR,KE) 1419500700003 ERR-ANALYS (DATA-ERR) No details on sources of error given 1419500700004 STATUS (TABLE) Data taken from Tab.1 of the reference 1419500700005 HISTORY (20160315C) 1419500700006 ENDBIB 4 0 1419500700007 NOCOMMON 0 0 1419500700008 DATA 4 13 1419500700009 E-MIN E-MAX DATA DATA-ERR 1419500700010 MEV MEV MEV MEV 1419500700011 0.14 0.3 0.282 0.007 1419500700012 0.3 0.5 0.759 0.019 1419500700013 0.5 0.7 0.963 0.024 1419500700014 0.7 1.0 0.908 0.023 1419500700015 1.0 1.5 1.044 0.026 1419500700016 1.5 2.0 0.778 0.020 1419500700017 2.0 2.5 0.660 0.017 1419500700018 2.5 3.0 0.503 0.013 1419500700019 3.0 4.0 0.550 0.014 1419500700020 4.0 5.0 0.254 0.010 1419500700021 5.0 6.0 0.102 0.009 1419500700022 6.0 7.0 0.038 0.005 1419500700023 7.0 10.0 0.0019 0.0014 1419500700024 ENDDATA 15 0 1419500700025 ENDSUBENT 24 0 1419500799999 ENDENTRY 7 0 1419599999999