ENTRY 22732 20051107 21742273200000001 SUBENT 22732001 20051107 21742273200100001 BIB 17 54 2273200100002 TITLE Isomeric cross section ratio for the (N,2N) reaction on2273200100003 Sc-45 from 13.6 to 14.9-MeV. 2273200100004 AUTHOR (M.Bostan, M.N.Erduran, M.Sirin, M.Subasi) 2273200100005 REFERENCE (J,PR/C,56,918,1997) 2273200100006 INSTITUTE (2TUKANK) 2273200100007 (2TUKYTU) 2273200100008 REL-REF (N,22474001,M.SUBASI+,J,NSE,122,423,1996) Experimental2273200100009 details 2273200100010 FACILITY (LINAC,2TUKCNA) Neutron generator 'sames t-400'at 2273200100011 cnaem. 2273200100012 SAMPLE .Approximatelly 2 g of high-purity Sc2-O3 powder, 2273200100013 more than 99.9% purity, was pressed into a pellet of 2273200100014 13 mm diameter and 7-mm thickness. Thin Al-flux 2273200100015 monitor foils of same diameter as the sample were 2273200100016 attached in front of each sample. 2273200100017 METHOD (ACTIV) 2273200100018 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2273200100019 DECAY-MON (11-NA-24,14.959HR,DG,1369.0,1.0) 2273200100020 MONIT-REF (,R.KINSEY,R,ENDF-201,1979) 2273200100021 INC-SOURCE (D-T) The neutrons produced via the H-3(d,N)He-4 2273200100022 reaction. 2273200100023 DETECTOR (HPGE) A 82 cc. Hpge-detector. 2273200100024 The full energy peak efficiency of this detector is 2273200100025 known to be better than 2% overall inaccuracy from 60 2273200100026 to 1800-KeV gamma rays. 2273200100027 (SCIN) The neutron source strength is monitored by 2273200100028 means of an Ne-213 liquid scintillation counter with 2273200100029 pulse shape discrimination against gamma rays. 2273200100030 INC-SPECT .The samples were placed at different neutron emission 2273200100031 angles O, 30, 60, 90, 120, 130-degrees and irradiated 2273200100032 for approximately 1-hr at irradiation position, 2273200100033 depending on the target conditions, covering the 2273200100034 neutron energies from 13.6 to 14.9-MeV. The neutron 2273200100035 energy was determined by the technique based on the 2273200100036 activation ratio of Zr-90(N,2N)Zr-89 and 2273200100037 Nb-93(N,2N)Nb-92-m reaction products. 2273200100038 ADD-RES (THEO) Staistical model calculation 2273200100039 ERR-ANALYS The major uncertainties and their estimated values in 2273200100040 cross section measurements are similar to those given 2273200100041 in rel-ref. 2273200100042 (ERR-T).The total error in cross section values was 2273200100043 obtained by combining the individual errors in 2273200100044 quadrature. See table 1. 2273200100045 (ERR-1) The peak area determination was achieved with 2273200100046 2% uncertainty for both gamma lines, 271 and 1157-KeV,2273200100047 due to good counting statistics. 2273200100048 (ERR-2) The uncertainties in the determination of the 2273200100049 effective neutron flux and the photopeak efficiency of2273200100050 the gamma detector, including self-absorption and 2273200100051 counting geometry, were 3%. 2273200100052 (ERR-3) The error in the decay data used was less than2273200100053 1%. 2273200100054 HISTORY (20051106C) + + Compiled by S.M. 2273200100055 (20051107U) Last checking has been done. 2273200100056 ENDBIB 54 0 2273200100057 COMMON 3 3 2273200100058 ERR-1 ERR-2 ERR-3 2273200100059 PER-CENT PER-CENT PER-CENT 2273200100060 2. 3. 1. 2273200100061 ENDCOMMON 3 0 2273200100062 ENDSUBENT 61 0 2273200199999 SUBENT 22732002 20051107 21742273200200001 BIB 3 6 2273200200002 REACTION 1(21-SC-45(N,2N)21-SC-44-M,,SIG) 2273200200003 2(21-SC-45(N,2N)21-SC-44-G,,SIG) 2273200200004 RAD-DET 1(21-SC-44-M,DG) 2273200200005 2(21-SC-44-G,DG) 2273200200006 DECAY-DATA1(21-SC-44-M,2.44D,DG,272.1,0.866) 2273200200007 2(21-SC-44-G,3.93HR,DG,1157.,0.999) 2273200200008 ENDBIB 6 0 2273200200009 NOCOMMON 0 0 2273200200010 DATA 5 6 2273200200011 EN DATA 1ERR-T 1DATA 2ERR-T 2 2273200200012 MEV MB MB MB MB 2273200200013 13.60 79.46 5.2 111.76 10.4 2273200200014 13.68 81.86 5.3 119.50 10.9 2273200200015 14.10 99.4 6.4 149.03 13.58 2273200200016 14.46 120.11 7.5 185.93 16.35 2273200200017 14.72 129.61 8.3 203.15 18.43 2273200200018 14.86 134.5 8.4 222.68 19.74 2273200200019 ENDDATA 8 0 2273200200020 ENDSUBENT 19 0 2273200299999 SUBENT 22732003 20051107 21742273200300001 BIB 3 11 2273200300002 REACTION (21-SC-45(N,2N)21-SC-44-M/G,,SIG/RAT) 2273200300003 ANALYSIS . Isomeric cross section ratios were 2273200300004 determined by applying the method of least squares to 2273200300005 the time behavior of the ground-state decay of 2273200300006 isomeric pair. The absolute cross section for the 2273200300007 formation of the metastable state was measured by the 2273200300008 usual activation technique. The ground-state cross 2273200300009 section was obtained by using the absolute cross 2273200300010 section of the metastable state and isomeric cross 2273200300011 section ratio for each neutron energy. 2273200300012 STATUS (DEP,22732002) 2273200300013 ENDBIB 11 0 2273200300014 NOCOMMON 0 0 2273200300015 DATA 3 6 2273200300016 EN DATA ERR-T 2273200300017 MEV NO-DIM NO-DIM 2273200300018 13.6 0.711 0.047 2273200300019 13.68 0.685 0.044 2273200300020 14.1 0.667 0.043 2273200300021 14.46 0.646 0.04 2273200300022 14.72 0.638 0.041 2273200300023 14.86 0.604 0.038 2273200300024 ENDDATA 8 0 2273200300025 ENDSUBENT 24 0 2273200399999 ENDENTRY 3 0 2273299999999