ENTRY 22826 20130110 22342282600000001 SUBENT 22826001 20130110 22342282600100001 BIB 19 69 2282600100002 TITLE .Cross section measurements for the 97-Mo(n,p)97m-Nb 2282600100003 reaction at the neutron energies from 13.6 to 14.9 MeV2282600100004 AUTHOR (M.Bostan,E.Gueltekin,I.A.Reyhancan) 2282600100005 INSTITUTE (2TUKSTU) Bostan, Gueltekin 2282600100006 (2TUKCNA) Reyhancan 2282600100007 REFERENCE (J,ANE,30,1821,2003) Main reference, data given 2282600100008 REL-REF (I,22478001,M.Subasi+,J,NSE,130,254,1998) Experimental2282600100009 details 2282600100010 (I,22392001,E.Gueltekin+,J,ANE,28,53,2001) Details of 2282600100011 the fast sample transfer system 2282600100012 (I,22474001,M.Subasi+,J,NSE,122,423,1996) Details of 2282600100013 the germanium high-purity detector 2282600100014 (M,22661001,E.Gueltekin+,J,ANE,29,2019,2002) Experim. 2282600100015 details 2282600100016 (M,,B.Accus+,J,ANE,28,437,2001) Description of the 2282600100017 two-crystal time-of-flight method 2282600100018 (M,,B.Anders,R,GKSS-83-E25,1983) Description of the 2282600100019 cyclic activation method 2282600100020 (R,22156015,T.Katoh+,S,JAERI-M-89-083,1989) Cross 2282600100021 section for 98Mo(n,n+p) 2282600100022 FACILITY (VDG,2TUKCNA) Neutron generator 'SAMES T-400'. 2282600100023 Terminal voltage is 300 KV, average beam current 500 2282600100024 micro-Amperes 2282600100025 INC-SOURCE (D-T) 2282600100026 INC-SPECT .Angles of irradiation of the target by deuterium ion 2282600100027 beam are 0, 30, 60, 90, 120 and 130 degrees. Effective2282600100028 mean neutron energy at each sample position had been 2282600100029 previously determined by the ratio of 90Zr(n,2n)89Zr 2282600100030 and 93Nb(n,2n)92m-Nb cross sections 2282600100031 .Neutron fluxes ranged from 1.E+7 to 6.E+7 n/cm2/sec 2282600100032 ANALYSIS .Cross sections were derived from the cyclic activation2282600100033 formulas given by B.Anders, see REL-REF no.4 2282600100034 METHOD (ACTIV) Activation 2282600100035 (TOF) Two-crystal time-of-flight method 2282600100036 (STTA) Stack target irradiation 2282600100037 PART-DET (G,N) 2282600100038 DETECTOR (HPGE) Coaxial detector 'CANBERRA', volume 82 cm3 with 2282600100039 1.79 keV full width at half-maximum of 1333 keV 2282600100040 gamma-energy. 2282600100041 (SCIN) Plastic scintillation detector NE102A 25 mm 2282600100042 diam, 0.5 mm thick for neutron flux monitoring2282600100043 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 2282600100044 DECAY-MON (12-MG-27,9.458MIN,DG,843.8,0.73) 2282600100045 MONIT-REF (41240000,A.Filatenkov+,R,INDC(CCP)-402,1997) 2282600100046 CORRECTION .Corrections were made for self-absorption of gammas 2282600100047 in samples, random coincidence, dead time, contribu- 2282600100048 tion of (n,np+nd) reaction due to 98Mo admixture, 2282600100049 low energy neutron contribution (aprx 21%) and 2282600100050 fluctuation of neutron flux 2282600100051 ADD-RES (THEO) Statistical model calculation 2282600100052 ERR-ANALYS (ERR-T) Total error 2282600100053 (ERR-1) Error of the sample weight 2282600100054 (ERR-2) Error due to concentration of the elements 2282600100055 in samples 2282600100056 (ERR-3) Error due to counting solid angle and 2282600100057 intrinsic efficiency of the gamma detector 2282600100058 (ERR-4,6.,8.) Error due to full energy photo-peak area2282600100059 (ERR-5) Error due to self-absorption of gamma rays 2282600100060 (ERR-6) Error due to gamma-gamma coincidence summing 2282600100061 (ERR-7) Error due to neutron flux fluctuations 2282600100062 (ERR-8,4.,6.) Error due to low energy neutrons 2282600100063 (ERR-9) Error of irradiation, cooling and measuring 2282600100064 times 2282600100065 (MONIT-ERR) Error due to effective neutron flux 2282600100066 = reference cross section 2282600100067 HISTORY (20040202C) + + J.O.S. 2282600100068 (20040202U) Last checking has been done. 2282600100069 (20130110A) SD: Facility was corrected (LINAC -> VDG) 2282600100070 ERR-ANALYS was corrected. 2282600100071 ENDBIB 69 0 2282600100072 COMMON 8 6 2282600100073 ERR-1 ERR-2 ERR-3 ERR-5 ERR-6 ERR-7 2282600100074 ERR-9 MONIT-ERR 2282600100075 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2282600100076 PER-CENT PER-CENT 2282600100077 0.1 1. 3. 1. 1. 0.12282600100078 0.1 3. 2282600100079 ENDCOMMON 6 0 2282600100080 ENDSUBENT 79 0 2282600199999 SUBENT 22826002 20040202 00002282600200001 BIB 4 9 2282600200002 REACTION (42-MO-97(N,P)41-NB-97-M,,SIG) 2282600200003 DECAY-DATA (41-NB-97-M,58.70SEC,DG,743.4,0.9790) 2282600200004 SAMPLE .Molybdenum oxide powder Mo-O3, 99% purity, pressed to 2282600200005 pellets 13 mm diameter, 8 mm thick, in stainless 2282600200006 steel capsules, weight aprx 3.5 gram, natural isotopic2282600200007 abundance, Mo-97 content is 9.55+-0.08% 2282600200008 .Aluminium oxide monitor sample Al2-O3 13 mm diameter 2282600200009 ERR-ANALYS (ERR-HL) Error of the half-life 2282600200010 (ERR-IDD) Error of the decay gamma intensity 2282600200011 ENDBIB 9 0 2282600200012 COMMON 2 3 2282600200013 ERR-HL ERR-IDD 2282600200014 SEC NO-DIM 2282600200015 0.18 0.0006 2282600200016 ENDCOMMON 3 0 2282600200017 DATA 4 6 2282600200018 EN EN-ERR DATA ERR-T 2282600200019 MEV MEV MB MB 2282600200020 13.60 0.80 3.25 0.30 2282600200021 13.68 0.81 3.28 0.32 2282600200022 14.10 0.10 4.13 0.41 2282600200023 14.46 0.11 5.37 0.60 2282600200024 14.72 0.11 5.30 0.63 2282600200025 14.86 0.12 4.60 0.55 2282600200026 ENDDATA 8 0 2282600200027 ENDSUBENT 26 0 2282600299999 ENDENTRY 2 0 2282699999999