ENTRY 14177 20130131 13861417700000001 SUBENT 14177001 20130131 13861417700100001 BIB 14 64 1417700100002 TITLE Inelastic partial gamma ray cross sections of 150Sm+n 1417700100003 reactions for En = 1-15 MeV 1417700100004 AUTHOR (D.Dashdorj,T.Kawano,G.E.Mitchell,J.A.Becker, 1417700100005 P.E.Garrett,M.Devlin,N.Fotiades,R.O.Nelson,S.Kunieda) 1417700100006 INSTITUTE (1USANCS,1USALAS,1USATNL,1USALRL,1CANGUE,2JPNJAE) 1417700100007 (3MGLMGL) MonAme Scientific Research Center, 1417700100008 Ulaanbaatar 1417700100009 REFERENCE (S,AIP-1342,9,2011) AIP2011 - Full set of data 1417700100010 (S,AIP-1005,164,2008) Only data for 439 and 505 keV 1417700100011 gamma transitions 1417700100012 FACILITY (LINAC,1USALAS) Experiment performed at the 1417700100013 Los Alamos Neutron Science Center (LANSCE)using 800 1417700100014 MeV proton linac 1417700100015 DETECTOR (HPGE) The gamma rays were detected with the GEANIE 1417700100016 spectrometer, located about 20 m from the neutron 1417700100017 source on the 60deg right flight path. For this 1417700100018 experiment, the GEANIE spectrometer consisted of 11 1417700100019 planar and 15 25% High- purity Ge (HPGe) coaxial 1417700100020 detectors. All of the planars and 9 of the coaxial 1417700100021 detectors were equipped with Compton suppression 1417700100022 shields. The detectors were situated at a distance of 1417700100023 approx. 14 cm from the focal point where the 1417700100024 scattering sample was located. 1417700100025 METHOD (TOF) neutron energy determined by time of flight 1417700100026 method. Detection time of the "flash" of gamma rays 1417700100027 caused by the spallation reaction was used as a 1417700100028 reference marker. The detection time of the gamma rays 1417700100029 produced by neutrons interacting with the sample was 1417700100030 used to calculate the time of flight. 1417700100031 MONITOR (92-U-235(N,F),,SIG) 1417700100032 (92-U-238(N,F),,SIG) 1417700100033 A fission chamber containing 235,238U located 2m 1417700100034 upstream from the GEANIE spectrometer was used to 1417700100035 determine the neutron flux. 1417700100036 (26-FE-56(N,INL)26-FE-56,PAR,SIG,G) Cross section for 1417700100037 production of 847 keV gamma transition was used 1417700100038 for checking purposes in several runs. For this 1417700100039 purpose the 150Sm sample was sandwiched between 1417700100040 0.2mm Fe foils. 1417700100041 INC-SOURCE (SPALL) Pulsed neutron beam was produced via 1417700100042 spallation on a natural W target by an 800-MeV proton 1417700100043 linear accelerator beam. The average proton beam 1417700100044 current at the spallation target was about 1 - 2 1417700100045 mu-A. The neutron beam structure contained 625 mu-s 1417700100046 long 'macropulses' driven by two of every three such 1417700100047 macropulses from the accelerator for an average rate 1417700100048 of 40/s. Each macropulse consisted of 'micropulses' 1417700100049 spaced every 1.8 mu-s, each <1 ns long. The pulsed 1417700100050 beam allowed incident neutron energies to be 1417700100051 determined using the time-of-flight technique. 1417700100052 SAMPLE (62-SM-150,ENR=0.956) The 150Sm sample with thickness 1417700100053 of 1550 mg/cm2 1417700100054 CORRECTION Corrected for internal conversion and deadtime and 1417700100055 multiple scattering. The internal conversion 1417700100056 coefficients were taken from the NUDAT database 1417700100057 COMMENT Cross sections for several discrete gamma rays i.e. 1417700100058 334 keV gamma line was already published in 2007 and 1417700100059 compiled in 14148.002. 1417700100060 ERR-ANALYS (EN-ERR) uncertainty of incident neutron energy 1417700100061 obtained from time-of-flight time resolution 1417700100062 (DATA-ERR) No information given 1417700100063 HISTORY (20080821C) Compiled by S.H. 1417700100064 (20130130D) Entry deleted, combined with entry 14148. 1417700100065 Data moved to 14148. 1417700100066 ENDBIB 64 0 1417700100067 NOCOMMON 0 0 1417700100068 ENDSUBENT 67 0 1417700199999 NOSUBENT 14177002 20130130 13861417700200001 NOSUBENT 14177003 20130130 13861417700300001 ENDENTRY 3 0 1417799999999