ENTRY 30928 20180523 31853092800000001 SUBENT 30928001 20180523 31853092800100001 BIB 17 59 3092800100002 TITLE Radiative capture of fast neutrons in 160Gd 3092800100003 AUTHOR (R.K.Y.Singh, M.Afzal Ansari, R.P.Gautam, I.A.Rizvi, 3092800100004 S.Kailas) 3092800100005 INSTITUTE (3INDMUA,3INDTRM) 3092800100006 REFERENCE (J,CJP,66,330,1988) 3092800100007 FACILITY (VDG,3INDTRM) 3092800100008 SAMPLE 160Gd2O3 powder with an isotopic enrichment of 98.1%. 3092800100009 The samples were prepared within a 1.6 cm dia. perspex 3092800100010 ring and sandwiched between two thin cellulose tapes. 3092800100011 The weighing was done up to an accuracy of 0.01 mg. 3092800100012 (64-GD-160,ENR=0.981) 3092800100013 (64-GD-158,ENR=0.0094) 3092800100014 (64-GD-157,ENR=0.0044) 3092800100015 (64-GD-156,ENR=0.0033) 3092800100016 (64-GD-155,ENR=0.0018) 3092800100017 MONITOR (53-I-127(N,G)53-I-128,,SIG) 3092800100018 MONIT-REF (,D.I.Garber+,R,BNL-325,1976) 3092800100019 DECAY-MON (53-I-128,,DG,443.,0.16) 3092800100020 INC-SOURCE (P-LI7,P-T) 3092800100021 Neutrons of 0.46, 0.57, and 0.75 MeV were obtained 3092800100022 from the Li-7(p,n)Be-7 reaction, and neutrons of 3092800100023 0.97, 1.22, 1.52, 2.22, and 3.05 MeV were obtained 3092800100024 from the He-3(p,n)He-3 reaction. 3092800100025 Lithium targets with a thickness of 300 ug/cm**2 were 3092800100026 prepared by vacuum evaporation on a thin tantalum 3092800100027 backing. 3092800100028 A very thin gold layer, a few ug/cm**2, was deposited 3092800100029 on the top of lithium. The tritium targets were 3092800100030 comprised of 12 and 16 Curie tritium absorbed in a 3092800100031 titanium layer on a thin copper backing having a 3092800100032 thickness of 0.25 mm. 3092800100033 METHOD (ACTIV) Sample was placed between two standard 3092800100034 samples of K-I of similar size. 3092800100035 Neutron flux at the place of irradiation was found to 3092800100036 be in the order of 10E+7 neutrons/cm**2/sec. 3092800100037 DETECTOR (GELI) 100 cm3 ORTEC Ge(Li) detector 3092800100038 (BF3) 4pi BF3 counter to monitor neutron flux 3092800100039 INC-SPECT (EN-RSL-HW) Total neutron-energy spread from 3092800100040 1. Energy spread in the proton beam 20 keV. 3092800100041 2. Degradation of incident beam in the T target 210 3092800100042 to 140 keV for a proton-beam energy of between 1 3092800100043 and 3 MeV. The corresponding neutron-energy spread 3092800100044 lies between 190 and 130 keV. 3092800100045 3. Angle subtended by the sample at the neutron 3092800100046 source 22 - 55 keV. 3092800100047 ERR-ANALYS (DATA-ERR) The cross-section errors contain 3092800100048 statistical and systematic uncertainties, including 3092800100049 the uncertainty in the cross section of the standard 3092800100050 reaction. 3092800100051 COMMENT See EXFOR 30678.002 and 30692.002 for similar 3092800100052 experiment at different energies. 3092800100053 STATUS (TABLE) Table 1 of Can.J.Phys.66(1988)330, 3092800100054 which mentions that the error analysis is the same as 3092800100055 in EXFOR 30678. 3092800100056 HISTORY (19881125C) TMK 3092800100057 (20090912A) SD: Codes for partial uncertainties and 3092800100058 data to COMMON section were added in Subent 001. 3092800100059 (20120502U) On. SAMPLE: Coded information introduced. 3092800100060 (20180523A) On. Major revision in 002. 3092800100061 ENDBIB 59 0 3092800100062 NOCOMMON 0 0 3092800100063 ENDSUBENT 62 0 3092800199999 SUBENT 30928002 20180523 31853092800200001 BIB 3 4 3092800200002 REACTION (64-GD-160(N,G)64-GD-161,,SIG) 3092800200003 DECAY-DATA (64-GD-161,,DG,315.,0.229, 3092800200004 DG,361.,0.606) 3092800200005 HISTORY (20180523A) On. EN-ERR -> EN-RSL-HW, ERR-T -> DATA-ERR 3092800200006 ENDBIB 4 0 3092800200007 NOCOMMON 0 0 3092800200008 DATA 4 8 3092800200009 EN EN-RSL-HW DATA DATA-ERR 3092800200010 MEV MEV MB MB 3092800200011 0.460 0.040 23.7 3.3 3092800200012 0.570 0.040 33.5 5.7 3092800200013 0.750 0.040 30.9 2.6 3092800200014 0.970 0.200 35.6 5.5 3092800200015 1.220 0.190 28.5 3.4 3092800200016 1.520 0.170 29.9 2.8 3092800200017 2.220 0.170 15.9 2.2 3092800200018 3.050 0.180 8.1 1.7 3092800200019 ENDDATA 10 0 3092800200020 ENDSUBENT 19 0 3092800299999 ENDENTRY 2 0 3092899999999