ENTRY 14513 20190119 14481451300000001 SUBENT 14513001 20190119 14481451300100001 BIB 12 43 1451300100002 TITLE Total kinetic energy release in the fast neutron 1451300100003 induced fission of 235U 1451300100004 AUTHOR (R.Yanez,J.King,J.S.Barrett,W.Loveland, 1451300100005 N.Fotiades,H.Y.Lee) 1451300100006 INSTITUTE (1USAORU,1USALAS) 1451300100007 REFERENCE (J,NP/A,970,65,2018) 1451300100008 FACILITY (LINAC,1USALAS) Experiment performed at Los Alamos 1451300100009 National Laboratory- Los Alamos Neutron Science 1451300100010 Center-Weapons Neutron Research 1451300100011 SAMPLE (92-U-235,ENR=0.9812) The 235U target consisted of a 1451300100012 2 cm diameter circular deposit of 235UF(4) on a thin 1451300100013 C backing. The thickness of the 235U was 175.5 mu-g 1451300100014 235U/cm2. Thickness of C backing was 100 mu-g/cm2. 1451300100015 The target was tilted at 45deg with respect to the 1451300100016 incident beam. 1451300100017 DETECTOR (SI) Two arrays of four Si PIN photodiodes were used 1451300100018 to detect the fission products, where the photodiodes 1451300100019 were arranged on opposite sides of the beam at angles 1451300100020 60deg and 120deg from the incident beam. The 1451300100021 individual PIN diodes had an area of 1 cm2, and the 1451300100022 detectors were 2.1 cm from the center of the target. 1451300100023 The timing pulse from a Si PIN diode coupled with the 1451300100024 accelerator RF signal were employed to measure the 1451300100025 time of flight of each interacting neutron. The 1451300100026 uncertainty of the position of the photofission peak 1451300100027 in the TOF spectrum was found to be 2.4%. 1451300100028 METHOD (TOF) Neutron energy was determined by time of 1451300100029 flight. The 625 mu-s macropulse proton beam contains 1451300100030 340 micropulses of width 250 ps that are spaced 1.8 1451300100031 mus apart, where the macropulses had a repetition 1451300100032 rate of 100 Hz. The distance from the spallation target1451300100033 to the Th target was measured to be 1384.9+-1.1 cm. 1451300100034 The 15R beam line with 13.85m flight path was used in 1451300100035 this experiment. 1451300100036 INC-SOURCE (SPALL) Neutron beams were generated from an 1451300100037 unmoderated tungsten spallation source using an 1451300100038 800MeV proton beam. Neutron time of flight and energy 1451300100039 was calculated via the proton accelerator pulse timing.1451300100040 CORRECTION Data were corrected for the pulse height defect in 1451300100041 Si PIN diode detectors and the energy losses of the 1451300100042 fragments in the target and backing foil 1451300100043 ERR-ANALYS (DATA-ERR) Source of uncertainties not described 1451300100044 HISTORY (20190119C) Compiled by S.H. 1451300100045 ENDBIB 43 0 1451300100046 NOCOMMON 0 0 1451300100047 ENDSUBENT 46 0 1451300199999 SUBENT 14513002 20190119 14481451300200001 BIB 3 3 1451300200002 REACTION (92-U-235(N,F),SEC,AKE,LF+HF) 1451300200003 STATUS (TABLE) Data taken from tab. 1 of the reference 1451300200004 MISC-COL (MISC) Mean bin energy 1451300200005 ENDBIB 3 0 1451300200006 NOCOMMON 0 0 1451300200007 DATA 6 20 1451300200008 EN-MIN EN-MAX DATA DATA-ERR MISC MISC-ERR 1451300200009 MEV MEV MEV MEV MEV MEV 1451300200010 2.16 2.52 168.9 0.6 2.36 0.01 1451300200011 2.52 2.90 169.0 0.6 2.71 0.01 1451300200012 2.90 3.35 168.9 0.5 3.11 0.01 1451300200013 3.35 3.93 168.9 0.5 3.62 0.01 1451300200014 3.93 4.65 168.2 0.5 4.28 0.02 1451300200015 4.65 5.55 168.2 0.6 5.08 0.02 1451300200016 5.55 6.72 167.9 0.6 6.14 0.03 1451300200017 6.72 7.85 167.3 0.5 7.28 0.04 1451300200018 7.85 9.26 166.9 0.5 8.54 0.05 1451300200019 9.26 11.25 166.9 0.5 10.19 0.07 1451300200020 11.25 14.00 166.4 0.6 12.57 0.09 1451300200021 14.00 17.65 165.4 0.5 15.72 0.13 1451300200022 17.65 22.40 165.0 0.6 19.93 0.18 1451300200023 22.40 28.10 164.1 0.5 25.09 0.26 1451300200024 28.10 35.20 163.6 0.6 31.45 0.37 1451300200025 35.20 42.90 162.5 0.5 38.9 0.5 1451300200026 42.90 52.10 163.0 0.5 47.35 0.68 1451300200027 52.10 63.40 162.1 0.5 57.73 0.92 1451300200028 63.40 80.00 162.1 0.5 71.45 1.28 1451300200029 80.00 100.00 161.5 0.5 89.71 1.83 1451300200030 ENDDATA 22 0 1451300200031 ENDSUBENT 30 0 1451300299999 ENDENTRY 2 0 1451399999999