ENTRY 14096 20110519 13721409600000001 SUBENT 14096001 20110519 13721409600100001 BIB 15 38 1409600100002 INSTITUTE (1USARIC) 1409600100003 REFERENCE (J,NP,23,116,1961) 1409600100004 AUTHOR (T.W.Bonner) 1409600100005 TITLE Measurements of neutron spectra from fission 1409600100006 FACILITY (REAC,1USAINL) the M.T.R. reactor in Idaho. 1409600100007 INC-SOURCE The foils were placed in a beam of predominately 1409600100008 thermal neutrons 1409600100009 METHOD Sphere-counter method 1409600100010 ANALYSIS Neutron energy derived from fission fragment kinetic 1409600100011 energy measurement 1409600100012 DETECTOR (TELES) Sphere moderated neutron spectrometer. The 1409600100013 sphere-counter was placed 2.8 m above the top shield 1409600100014 of the reactor. 1409600100015 MONITOR The DE and E silicon detectors were calibrated using a 1409600100016 226Ra a source. 1409600100017 SAMPLE The samples to be observed were foils of U 235, U 233, 1409600100018 and Pu 239 with a thickness from 0.025 to 0.050 cm and1409600100019 an area of about 20 cm2. The samples were placed 1409600100020 35 cm from the centre of the counter 1409600100021 CORRECTION Background counts were made with a cadmium shutter 1409600100022 covering the port in the reactor so that effects due 1409600100023 to all but thermal neutrons were eliminated. A small 1409600100024 correction has been made to subtract the counts due to1409600100025 delayed neutrons whose relative abundance as compared 1409600100026 to prompt neutrons amounts to 0.64 %, 0.26 %, and 1409600100027 0.22 % respectively or U 235, U 233 and Pu 239. 1409600100028 The average energy of the delayed neutrons used in 1409600100029 this calculation was 0.45 MeV. 1409600100030 STATUS (TABLE) Data taken from table 6 and average fission 1409600100031 neutron energy given as in REL-REF 1409600100032 REL-REF (N,,A.B.Smith,C,71VIENNA,,3,1971) 1409600100033 "Prompt Fission Neutron Spectra", A. B. Smith, 1409600100034 Proceedings of a consultant's meeting on prompt fission1409600100035 neutron spectra, publ. by IAEA (1972), page 3 1409600100036 HISTORY (20060518C) DR 1409600100037 (20061120A) DR EN-DUMMY changed to EN 1409600100038 (20101122A) OS. BIB changes, REACTION codes corrected 1409600100039 (20110513A) OS. Corr. in subentry 6 1409600100040 ENDBIB 38 0 1409600100041 COMMON 1 3 1409600100042 EN 1409600100043 EV 1409600100044 0.0253 1409600100045 ENDCOMMON 3 0 1409600100046 ENDSUBENT 45 0 1409600199999 SUBENT 14096002 20110124 13701409600200001 BIB 3 3 1409600200002 REACTION (92-U-233(N,F)0-NN-1,PR,KE,,,DERIV) 1409600200003 ERR-ANALYS No error given 1409600200004 HISTORY (20101122A) OS. REACTION SF6 changed from AKE to KE 1409600200005 ENDBIB 3 0 1409600200006 NOCOMMON 0 0 1409600200007 DATA 1 1 1409600200008 DATA 1409600200009 MEV 1409600200010 1.998 1409600200011 ENDDATA 3 0 1409600200012 ENDSUBENT 11 0 1409600299999 SUBENT 14096003 20110124 13701409600300001 BIB 3 3 1409600300002 REACTION (92-U-235(N,F)0-NN-1,PR,KE,,,DERIV) 1409600300003 ERR-ANALYS No error given 1409600300004 HISTORY (20101122A) OS. REACTION SF6 changed from AKE to KE 1409600300005 ENDBIB 3 0 1409600300006 NOCOMMON 0 0 1409600300007 DATA 1 1 1409600300008 DATA 1409600300009 MEV 1409600300010 2.034 1409600300011 ENDDATA 3 0 1409600300012 ENDSUBENT 11 0 1409600399999 SUBENT 14096004 20110124 13701409600400001 BIB 3 3 1409600400002 REACTION (94-PU-239(N,F)0-NN-1,PR,KE,,,DERIV) 1409600400003 ERR-ANALYS No error given 1409600400004 HISTORY (20101122A) OS. REACTION SF6 changed from AKE to KE 1409600400005 ENDBIB 3 0 1409600400006 NOCOMMON 0 0 1409600400007 DATA 1 1 1409600400008 DATA 1409600400009 MEV 1409600400010 2.077 1409600400011 ENDDATA 3 0 1409600400012 ENDSUBENT 11 0 1409600499999 SUBENT 14096005 20110124 13701409600500001 BIB 3 3 1409600500002 REACTION (94-PU-240(N,F)0-NN-1,PR,KE,,,DERIV) 1409600500003 ERR-ANALYS No error given 1409600500004 HISTORY (20101122A) OS. REACTION SF6 changed from AKE to KE 1409600500005 ENDBIB 3 0 1409600500006 NOCOMMON 0 0 1409600500007 DATA 1 1 1409600500008 DATA 1409600500009 MEV 1409600500010 1.738 1409600500011 ENDDATA 3 0 1409600500012 ENDSUBENT 11 0 1409600599999 SUBENT 14096006 20110519 13721409600600001 BIB 3 4 1409600600002 REACTION (94-PU-240(N,F)0-NN-1,PR,KE,,,DERIV) 1409600600003 ERR-ANALYS No error given 1409600600004 HISTORY (20101122A) OS. REACTION SF6 changed from AKE to KE 1409600600005 (20110513A) OS. Deleted SF7. 1409600600006 ENDBIB 4 0 1409600600007 NOCOMMON 0 0 1409600600008 DATA 1 1 1409600600009 DATA 1409600600010 MEV 1409600600011 2.050 1409600600012 ENDDATA 3 0 1409600600013 ENDSUBENT 12 0 1409600699999 ENDENTRY 6 0 1409699999999