ENTRY 14460 20161026 14261446000000001 SUBENT 14460001 20161026 14261446000100001 BIB 10 39 1446000100002 TITLE Measurement of neutron capture on 136Xe 1446000100003 AUTHOR (J.B.Albert,S.J.Daugherty,T.N.Johnson,T.O'Conner, 1446000100004 L.J.Kaufman,A.Couture,J.L.Ullmann,M.Krticka) 1446000100005 INSTITUTE (1USAINU,1USALAS,3CZRCHU) 1446000100006 REFERENCE (J,PR/C,94,034617,2016) 1446000100007 FACILITY (LINAC,1USALAS) Experiment performed at the Manuel 1446000100008 Lujan Jr. Neutron Scattering Center at the Los Alamos 1446000100009 Neutron Science Center. 1446000100010 SAMPLE (54-XE-136,ENR=0.999) Gaseous 136Xe sample was 3 cm 1446000100011 thick sample pressurized to an average of 26 psi. The 1446000100012 xenon gas was contained in an aluminum cell with 2.9 1446000100013 cm diameter, 0.003 inch thick kapton windows allowing 1446000100014 the neutron beam to pass through. The beam diameter 1446000100015 was smaller than 2 cm at the target, the full flux of 1446000100016 neutrons was incident upon xenon. 1446000100017 DETECTOR (BAF2) Capture gamma rays were registered using array 1446000100018 DANCE, consisting of 160 BaF2 crystals arranged 1446000100019 spherically around the target. Each crystal is 15 cm 1446000100020 long, has a volume of 734 cm3. The DANCE array covers 1446000100021 solid angle of approx. 3.5 Pi steradians. 1446000100022 METHOD (TOF) Incident neutron energy was determined by time 1446000100023 of flight. DANCE was located on Flight Path 14.This 1446000100024 flight path is exposed to neutrons that pass through 1446000100025 a room-temperature water moderator. The target sample, 1446000100026 centered within the detector, is 20.25 m downstream 1446000100027 of the moderator. The data was collected by two 1446000100028 digitizers each recording a 256 ms long window. These 1446000100029 time windows were set to a delay relative to the 1446000100030 initial neutron beam trigger to select specific 1446000100031 neutron energies based on time of flight. The first 1446000100032 time window was set to look at the high neutron 1446000100033 energy events, including the 2.154 keV 136Xe capture 1446000100034 resonance, the second was delayed by 9.15 ms to look 1446000100035 at the thermal neutron energy range of 0.0243 to 1446000100036 0.0256 eV. 1446000100037 INC-SOURCE (SPALL) Neutrons were produced by spallation reaction 1446000100038 of 800 MeV protons on tungsten target, Neutrons were 1446000100039 moderated using room temperature water moderator. 1446000100040 HISTORY (20161026C) Compiled by S.H. 1446000100041 ENDBIB 39 0 1446000100042 NOCOMMON 0 0 1446000100043 ENDSUBENT 42 0 1446000199999 SUBENT 14460002 20161026 14261446000200001 BIB 3 10 1446000200002 REACTION ((54-XE-136(N,G)54-XE-137,,SIG)// 1446000200003 (54-XE-136(N,G)54-XE-137,,INT)) 1446000200004 STATUS (TABLE) Data taken from text p.6 of the reference 1446000200005 ERR-ANALYS (ERR-1) systematic uncertainty of the flux ratio 1446000200006 (ERR-2) Systematic uncertainty of the efficiency ratio 1446000200007 (ERR-3) Systematic uncertainty in direct ratio 1446000200008 (ERR-4) Systematic uncertainty in Background 1446000200009 subtraction 1446000200010 (ERR-SYS) Systematic uncertainty 1446000200011 (ERR-S) Statistical uncertainty 1446000200012 ENDBIB 10 0 1446000200013 COMMON 4 3 1446000200014 ERR-1 ERR-2 ERR-3 ERR-4 1446000200015 PER-CENT PER-CENT PER-CENT PER-CENT 1446000200016 1.7 3.3 0.5 4.4 1446000200017 ENDCOMMON 3 0 1446000200018 DATA 7 1 1446000200019 EN-NM EN-RSL-NM EN-MIN-DN EN-MAX-DN DATA ERR-SYS 1446000200020 ERR-S 1446000200021 MILLI-EV MILLI-EV KEV KEV 1/MILLI-EV 1/MILLI-EV 1446000200022 1/MILLI-EV 1446000200023 25. 1.3 2.094 2.203 4.10 0.24 1446000200024 0.10 1446000200025 ENDDATA 6 0 1446000200026 ENDSUBENT 25 0 1446000299999 SUBENT 14460003 20161026 14261446000300001 BIB 5 8 1446000300002 REACTION (54-XE-136(N,G)54-XE-137,,SIG) 1446000300003 STATUS (TABLE) Data taken from text p.6 of the reference 1446000300004 (DEP,14460002) 1446000300005 ERR-ANALYS (DATA-ERR) Total uncertainty 1446000300006 MONITOR (54-XE-136(N,G)54-XE-137,,INT) 1446000300007 MONIT-REF (13159002,R.L.Macklin,R,ORNL-TM-1766,1988) 1446000300008 Capture kernel 30.1+/-1.5 meV was converted to the 1446000300009 cross section integral 58.0+/-2.9 b*eV by the author 1446000300010 ENDBIB 8 0 1446000300011 NOCOMMON 0 0 1446000300012 DATA 6 1 1446000300013 EN-MIN EN-MAX DATA DATA-ERR MONIT MONIT-ERR 1446000300014 EV EV B B B*EV B*EV 1446000300015 0.0243 0.0256 0.238 0.019 58.0 2.9 1446000300016 ENDDATA 3 0 1446000300017 ENDSUBENT 16 0 1446000399999 ENDENTRY 3 0 1446099999999