ENTRY 14098 20110124 13701409800000001 SUBENT 14098001 20110124 13701409800100001 BIB 13 25 1409800100002 INSTITUTE (1USAANL) 1409800100003 REFERENCE (J,NSE,44,439,1971) 1409800100004 AUTHOR (A.B.Smith) 1409800100005 TITLE Note on the prompt fission neutron spectra of uranium 1409800100006 235 and plutonium 239 1409800100007 FACILITY (REAC,1USAANL) 1409800100008 INC-SOURCE Neutron energies of 35 +/- 12 or 400 +/- 25 keV were 1409800100009 incident on the fissile samples in bursts of about 1 1409800100010 nsec duration 1409800100011 METHOD (TOF) 1409800100012 DETECTOR (SCIN) Proton recoil scintillation detectors were 1409800100013 placed about 200 cm from the fission sample 1409800100014 REL-REF (M,,A.Smith,J,NIM,50,277,1967) 1409800100015 MONITOR Neutron sensitivity of each detector was calibrated to 1409800100016 energies of 1.6 MeV relative to the differential 1409800100017 elastic scattering of carbon 1409800100018 SAMPLE The fissile samples were right cylinders 2 cm high and1409800100019 2 cm in diameter fabricated from material of more than1409800100020 94 % isotopic purity. 1409800100021 CORRECTION Correction for neutron attenuation and multiple 1409800100022 scattering within the samples and for finite angular 1409800100023 definition of the apparatus 1409800100024 HISTORY (20060519C) DR 1409800100025 (20101122A) OS. Subentry 2 deleted (no such data in 1409800100026 reference); REACTION in sub.3 corrected; REL-REF added1409800100027 ENDBIB 25 0 1409800100028 COMMON 2 3 1409800100029 EN-MIN EN-MAX 1409800100030 MEV MEV 1409800100031 0.03 0.4 1409800100032 ENDCOMMON 3 0 1409800100033 ENDSUBENT 32 0 1409800199999 NOSUBENT 14098002 20110124 13701409800200001 SUBENT 14098003 20110124 13701409800300001 BIB 4 6 1409800300002 REACTION ((94-PU-239(N,F)0-NN-1,PR,KE,,AV)/ 1409800300003 (92-U-235(N,F)0-NN-1,PR,KE,,AV)) 1409800300004 ERR-ANALYS (DATA-ERR,1.5,2.0) No details given 1409800300005 STATUS (TABLE) Data taken from text 1409800300006 HISTORY (20101122A) OS. REACTION SF6 changed from AKE to KE; 1409800300007 SF8=AV added. Uncertainty information modified. 1409800300008 ENDBIB 6 0 1409800300009 NOCOMMON 0 0 1409800300010 DATA 1 1 1409800300011 DATA 1409800300012 NO-DIM 1409800300013 1.075 1409800300014 ENDDATA 3 0 1409800300015 ENDSUBENT 14 0 1409800399999 ENDENTRY 3 0 1409899999999