ENTRY 31420 20100220 31443142000000001 SUBENT 31420001 20100220 31443142000100001 BIB 14 48 3142000100002 TITLE Production cross section measurement of discrete 3142000100003 gamma-ray at 90 deg. for interactions of 14.9 MeV 3142000100004 neutrons with carbon and niobium. 3142000100005 AUTHOR (Zhou Hongyu,Yan Yiming,Tanglin,Wen Shenlin, 3142000100006 Zhang Shenji,Hua Ming,Han Chongzhan,Ding Xiaoji, 3142000100007 Lan Liqiao,Fan Guoying,Yan Hua,Wang Xingfu,Wang Qi, 3142000100008 Sun Suxu,Rong Yaning,Liu Shuzhen) 3142000100009 INSTITUTE (3CPRBNU) Institute of low energy nuclear physics. 3142000100010 REFERENCE (J,CNP,11,(2),63,1989) 3142000100011 MONITOR The neutron flux was monitored with a liquid scintil- 3142000100012 lator (TOF) and by alpha-particle counting. 3142000100013 FACILITY (CCW,3CPRBNU) 400 KV Cockroft Walton accelerator 3142000100014 INC-SOURCE (D-T) Samples were placed on the deuteron beam axis, 3142000100015 13.4 cm away from the Ti target. 3142000100016 METHOD (TOF) Pulsed fast neutron beam was used. 3142000100017 DETECTOR (GELI) 3142000100018 CORRECTION -Neutron flux attenuation in the backing and cooling 3142000100019 water of the neutron target 3142000100020 -neutron attenuation in the sample 3142000100021 -neutron multiple scattering in the sample 3142000100022 -gamma-ray attenuation in the sample 3142000100023 -finite size of the neutron source 3142000100024 -counting loss of gamma rays with energy less than 3142000100025 180 keV induced by the bias and limited width of the 3142000100026 gating pulses of the Ge(Li) detector 3142000100027 -contributions of gamma rays from activities 3142000100028 induced by (n,p) and (n,2n) reactions. 3142000100029 -Background; background spectra were accumulated 3142000100030 with sample after the beam was stopped and in-beam 3142000100031 without sample. 3142000100032 ERR-ANALYS (ERR-T) The errors of cross sections were estimated 3142000100033 taking account of the uncertainties in 3142000100034 (ERR-S,1.,100.) the number of counts in the full 3142000100035 energy peak 1-100% 3142000100036 (ERR-1,,4.) the neutron flux < 4% 3142000100037 (ERR-2,1.5,3.) absolute detection efficiency 1.5-3.0% 3142000100038 (ERR-3,1.,3.) the correction factor of neutron and 3142000100039 gamma-yields in the determination of 3142000100040 the cross sections 1.- 3.0% 3142000100041 REL-REF (R,,C.M.Lederer,B,LEDERER-7,,379,1978) 3142000100042 The probable reaction types and transitions were taken 3142000100043 from level schemes in d.M.Lederer et al., Table of 3142000100044 isotopes, 1978, p. 379. 3142000100045 STATUS (TABLE) Data taken from Chin. Journal of Nucl. 3142000100046 Phys. Vol. 11,No. 2, 1989, pp.63-74 Tables 1 and 2. 3142000100047 HISTORY (19930908C) HW 3142000100048 (19940519U) HW.- Reaction code altered in subent 002.- 3142000100049 (20090730A) SD:Updated to new date formats,lower case. 3142000100050 ENDBIB 48 0 3142000100051 COMMON 2 3 3142000100052 EN ANG 3142000100053 MEV ADEG 3142000100054 14.9 90.0 3142000100055 ENDCOMMON 3 0 3142000100056 ENDSUBENT 55 0 3142000199999 SUBENT 31420002 20100220 31443142000200001 BIB 4 7 3142000200002 REACTION (6-C-12(N,INL)6-C-12,PAR,DA,G) 3142000200003 SAMPLE Natural graphite cylinder, 2.796 cm in diameter and 3142000200004 3.540 cm in height, 43.15 g in weight. 3142000200005 COMMENT According to the author the data in this subentry 3142000200006 supersede those in the previous subentry 30904002 3142000200007 ( from INDC(CPR)-10, 1986). 3142000200008 HISTORY (19930519U) HW.- Reaction code altered.- 3142000200009 ENDBIB 7 0 3142000200010 NOCOMMON 0 0 3142000200011 DATA 3 1 3142000200012 E DATA ERR-T 3142000200013 KEV MB/SR MB/SR 3142000200014 4439.0 11.48 0.80 3142000200015 ENDDATA 3 0 3142000200016 ENDSUBENT 15 0 3142000299999 SUBENT 31420003 20100220 31443142000300001 BIB 3 7 3142000300002 REACTION (41-NB-93(N,X)0-G-0,PAR,DA) 3142000300003 FLAG (1.) Probable reaction 41-Nb-93(n,inl) 3142000300004 (2.) probable reaction 41-Nb-93(n,2n)41-Nb-92 3142000300005 (3.) (1.) and from 1642..0 keV level of (2.). 3142000300006 COMMENT According to the author the data in this subentry 3142000300007 supersede those in the previous subentry 30904006 3142000300008 ( from INDC(CPR)-10, 1986). 3142000300009 ENDBIB 7 0 3142000300010 NOCOMMON 0 0 3142000300011 DATA 6 79 3142000300012 E DATA ERR-T LVL-INI LVL-INI FLAG 3142000300013 KEV MB/SR MB/SR KEV KEV NO-DIM 3142000300014 147.70 3.20 .48 2235.0 2.0 3142000300015 149.52000 16.52 1.50 285.0 2.0 3142000300016 155.90 .693 .180 1480.0 2.0 3142000300017 163.68000 12.96 1.52 389.1 2.0 3142000300018 194.47000 7.28 0.84 479.6 2.0 3142000300019 318.20000 1.30 0.16 1297.42 2003.38 3.0 3142000300020 338.44000 3.170 0.29 1082.74 2003.38 1.0 3142000300021 351.50000 0.602 0.124 1686.07 1.0 3142000300022 357.06000 19.04 1.09 357.06 2.0 3142000300023 364.50000 0.362 .330 1679.56 1.0 3142000300024 385.46000 5.36 0.40 1334.80 1.0 3142000300025 477.30000 1.12 0.42 1968.25 1.0 3142000300026 501.18000 20.89 1.23 501.18 2.0 3142000300027 537.61000 0.594 0.095 2203.20 1.0 3142000300028 541.25000 4.13 0.32 1491.15 1.0 3142000300029 553.00000 1.14 0.30 1297.42 1947.80 3.0 3142000300030 560.67000 1.39 0.37 1369.41 1.0 3142000300031 571.43000 1.10 0.18 1315.08 1.0 3142000300032 585.01000 1.39 0.24 1394.61 1.0 3142000300033 599.70 .773 .160 1682.82 2203.20 1.0 3142000300034 624.80000 0.566 .230 1603.80 2019.01 1.0 3142000300035 627.00000 0.617 .235 2118.59 1.0 3142000300036 653.69000 1.14 0.15 1603.80 1.0 3142000300037 656.26000 1.57 0.20 686.44 1.0 3142000300038 689.18000 2.04 0.46 2171.98 1.0 3142000300039 736.96000 0.757 0.334 1686.07 1.0 3142000300040 743.95000 13.17 0.80 743.95 1.0 3142000300041 762.95000 1.23 0.18 1738.0 2998.00 2.0 3142000300042 779.63000 4.93 0.43 1728.59 810.05 1.0 3142000300043 808.64000 4.70 0.35 808.64 1.0 3142000300044 863.70000 0.774 0.267 1089.00 2.0 3142000300045 876.14000 1.04 0.27 2367.31 1.0 3142000300046 908.20000 2.43 0.33 1410.20 2.0 3142000300047 919.54000 2.89 0.44 949.50 1728.59 1.0 3142000300048 923.90000 0.882 .240 3142000300049 934.40000 2.98 0.35 1414.00 2.0 3142000300050 949.89000 20.99 1.11 949.89 2203.20 1.0 3142000300051 979.01000 9.27 0.57 979.01 1.0 3142000300052 989.90000 0.400 .200 1968.25 1.0 3142000300053 1020.50 2.33 0.23 1968.25 1.0 3142000300054 1032.12 2.24 0.24 2329.90 2367.31 1.0 3142000300055 1052.66 1.16 0.36 1082.74 1.0 3142000300056 1066.27 1.79 0.40 3142000300057 1082.74 1.47 0.20 1082.74 1.0 3142000300058 1089.62 1.81 0.24 2171.98 1.0 3142000300059 1097.57 1.68 0.30 3142000300060 1122.40 1.89 0.25 3142000300061 1130.65 1.36 0.28 1632.00 2.0 3142000300062 1147.52 1.57 0.24 2482.89 1.0 3142000300063 1183.30 0.881 0.390 2133.20 1.0 3142000300064 1209.66 1.36 0.37 2019.01 1.0 3142000300065 1253.40 0.713 0.190 1253.40 1.0 3142000300066 1275.60 0.793 0.240 1411.00 2.0 3142000300067 1297.42 1.08 0.16 1297.42 1.0 3142000300068 1332.40 1.11 0.28 2019.01 1.0 3142000300069 1377.30 2.50 0.24 3142000300070 1425.10 0.588 .110 3142000300071 1443.93 1.59 0.32 1945.00 2.0 3142000300072 1482.60 1.03 0.20 1482.60 1.0 3142000300073 1499.98 2.03 0.22 1499.98 1.0 3142000300074 1549.00 1.01 0.23 3142000300075 1567.41 1.80 0.23 1567.41 1.0 3142000300076 1603.80 0.366 .200 1603.80 1.0 3142000300077 1626.80 0.980 .280 3142000300078 1820.80 1.00 0.24 3142000300079 1905.90 1.17 0.23 3142000300080 1910.50 0.963 .250 1910.50 1.0 3142000300081 1944.79 1.70 0.25 1944.79 2.0 3142000300082 1953.10 0.728 .300 3142000300083 1984.90 0.700 .310 3142000300084 2087.25 7.24 0.42 2087.25 2.0 3142000300085 2115.99 2.88 0.35 3142000300086 2164.70 1.16 0.26 2164.40 1.0 3142000300087 2213.32 0.981 .220 3142000300088 2286.67 2.91 0.31 2286.67 2.0 3142000300089 2307.42 1.68 0.22 3142000300090 2407.35 1.02 0.21 3142000300091 2432.28 0.875 .160 3142000300092 2507.50 0.916 .230 3142000300093 ENDDATA 81 0 3142000300094 ENDSUBENT 93 0 3142000399999 ENDENTRY 3 0 3142099999999