ENTRY 31457 20100307 31443145700000001 SUBENT 31457001 20100307 31443145700100001 BIB 11 20 3145700100002 TITLE Total neutron cross section of U-238 as measured 3145700100003 with filtered neutrons of 55 keV and 144 keV. 3145700100004 AUTHOR (Pham Zuy Hien,Vuong Huu Tang,Nguyen Phuoc Xuan) 3145700100005 INSTITUTE (3VN DAL) 3145700100006 REFERENCE (R,INDC(NDS)-265,199210) 3145700100007 (R,INDC(VN)-007,199510) in summary form only. 3145700100008 FACILITY (REAC,3VN DAL) Dalat nuclear research reactor. 3145700100009 INC-SOURCE (REAC) Filtered neutron beams of 55 keV and 144 keV 3145700100010 were produced. The flux intensities are 3145700100011 4.x 10**6 n/cm2/sec and 1.2 x 10**2/sec, respectevely. 3145700100012 DETECTOR (HPGE) Detection system consisted of a cylindrical 3145700100013 boron absorber (85% enriched in B-10) and a HPGe 3145700100014 detector counting the 480 keV gamma rays from the 3145700100015 B-10(n,alpha+gamma) reaction. 3145700100016 METHOD (FLUX) Incident and transmitted flux was measured. 3145700100017 ERR-ANALYS (DATA-ERR) No error analysis given. 3145700100018 HISTORY (19960426C) HW.- 3145700100019 (20100219A) SD:Updated to new date formats,lower case. 3145700100020 STATUS (TABLE) Data were taken from the text and Table 2 of 3145700100021 INDC(NDS)-265, October 1992. 3145700100022 ENDBIB 20 0 3145700100023 NOCOMMON 0 0 3145700100024 ENDSUBENT 23 0 3145700199999 SUBENT 31457002 20100307 31443145700200001 BIB 2 3 3145700200002 REACTION (6-C-12(N,TOT),,SIG) 3145700200003 SAMPLE Pellets or cylinders, 18 mm in diameter, 3145700200004 of nuclear grade graphite. 3145700200005 ENDBIB 3 0 3145700200006 NOCOMMON 0 0 3145700200007 DATA 3 2 3145700200008 EN DATA DATA-ERR 3145700200009 KEV B B 3145700200010 55. 4.37 0.15 3145700200011 144. 4.28 0.013 3145700200012 ENDDATA 4 0 3145700200013 ENDSUBENT 12 0 3145700299999 SUBENT 31457003 20100307 31443145700300001 BIB 2 3 3145700300002 REACTION (92-U-238(N,TOT),,SIG) 3145700300003 SAMPLE Pellets or cylinders, 18 mm in diameter, of metallic 3145700300004 depleted uranium with 0.22% U-235. 3145700300005 ENDBIB 3 0 3145700300006 NOCOMMON 0 0 3145700300007 DATA 3 2 3145700300008 EN DATA DATA-ERR 3145700300009 KEV B B 3145700300010 55. 13.31 .11 3145700300011 144. 11.52 .11 3145700300012 ENDDATA 4 0 3145700300013 ENDSUBENT 12 0 3145700399999 ENDENTRY 3 0 3145799999999