ENTRY 22478 20180830 22702247800000001 SUBENT 22478001 20180830 22702247800100001 BIB 19 60 2247800100002 TITLE .(n,alpha) reaction cross sections of 44Ca, 45Sc, 2247800100003 and 51V nuclei from 13.6 to 14.9 MeV 2247800100004 AUTHOR (M.Subasi,M.N.Erduran,M.Bostan,I.A.Reyhancan, 2247800100005 E.Gueltekin,G.Tarcan,Y.Ozbir,A.Durusoy) 2247800100006 INSTITUTE (2TUKCNA) Subasi, Gueltekin, Ozbir, Bostan, Erduran, 2247800100007 Tarkan, Reyhancan 2247800100008 (2TUKYTU) Durusoy 2247800100009 REFERENCE (J,NSE,130,254,1998) Main Reference 2247800100010 REL-REF (N,22474001,M.Subasi+,J,NSE,122,423,1996) Experimental2247800100011 Details 2247800100012 METHOD (ACTIV) Activation 2247800100013 (STTA) Stack target sample with aluminum backings 2247800100014 in front and at the rear of the ample 2247800100015 PART-DET (G) 2247800100016 DETECTOR (HPGE) Coaxial detector 'Canberra', volume 82 cm3 with 2247800100017 1.79 keV full width at half-maximum at 1333 keV 2247800100018 gamma-energy 2247800100019 FACILITY (VDG,2TUKCNA) Neutron generator 'SAMES T-400'. 2247800100020 terminal voltage is 300 kV, average beam current 500 2247800100021 micro-Amperes 2247800100022 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2247800100023 DECAY-MON (11-NA-24,14.959HR,DG,1368.0,1.0) 2247800100024 MONIT-REF (,R.Kinsey,R,ENDF-201,1979) 2247800100025 INC-SOURCE (D-T) 2247800100026 INC-SPECT .Angles of irradiation of the target by deuterium ion 2247800100027 beam are 0, 30, 60, 90, 120 and 130 degrees. Effective2247800100028 mean neutron energy at each sample position had been 2247800100029 previously determined by the ratio of 90Zr(n,2n)89Zr 2247800100030 and 93Nb(n,2n)92M-Nb cross sections 2247800100031 .Neutron fluxes ranged from 1.E+7 to 6.E+7 n/cm2/sec 2247800100032 SAMPLE .Model sample as a disk pellets 13 mm diameter, 8.5 mm 2247800100033 thickness pressed from high-purity (99.99%) oxides 2247800100034 Al2-O3, weight 1.5 gram, sandwiched between two 1-mm 2247800100035 thick aluminium foils. 2247800100036 CORRECTION .Corrections were made for gamma-ray attenuation in 2247800100037 samples and for neutron flux attenuation using the 2247800100038 activity difference between the front and back 2247800100039 aluminium foils. 2247800100040 ADD-RES (THEO) Statistical model calculation 2247800100041 ERR-ANALYS (ERR-T) Total error 2247800100042 (ERR-1) Error of the sample weight 2247800100043 (ERR-2) Error due to concentration of the elements 2247800100044 in samples 2247800100045 (ERR-3) Error due to the efficiency of gamma detector 2247800100046 and due to counting solid angle 2247800100047 (ERR-4,0.,4.0) Error due to gamma-gamma coincidence 2247800100048 summing 2247800100049 (ERR-5) Error due to self-absorption of gamma-rays 2247800100050 (ERR-6,1.,2.) Error due to full-energy photo-peak area 2247800100051 (ERR-7) Error due to neutron flux including 2247800100052 uncertainty of the reference cross-section 2247800100053 (ERR-8) Error of irradiation, cooling and measuring 2247800100054 times 2247800100055 (ERR-9) Error due to neutron flux fluctuations 2247800100056 (ERR-10,0.6,2.) Error due to low energy neutrons 2247800100057 HISTORY (20010611C) + + Compiled by S.M. 2247800100058 (20010611U) Last checking has been done. 2247800100059 (20121223U) SD: Type of facility was changed; 2247800100060 ERR-ANALYS update. 2247800100061 (20180830U) SD: Small correction in ERR-ANALYS. 2247800100062 ENDBIB 60 0 2247800100063 COMMON 8 6 2247800100064 ERR-1 ERR-2 ERR-3 ERR-5 ERR-7 ERR-8 2247800100065 ERR-9 EN-ERR 2247800100066 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2247800100067 PER-CENT MEV 2247800100068 0.1 0.5 3. 0.2 3. 0.12247800100069 0.1 0.1 2247800100070 ENDCOMMON 6 0 2247800100071 ENDSUBENT 70 0 2247800199999 SUBENT 22478002 20010611 00002247800200001 BIB 3 6 2247800200002 REACTION (20-CA-44(N,A)18-AR-41,,SIG) 2247800200003 DECAY-DATA (18-AR-41,1.822HR,DG,1297.0,0.9916) 2247800200004 SAMPLE .Sample As a Disk Pellets 13 mm Diameter, 8.5 mm 2247800200005 Thickness Pressed from High-Purity (99.99%) Oxides 2247800200006 Ca-O , Weight 1.5 Gram, Sandwiched Between Two 1-Mm 2247800200007 Thick Aluminium Foils, Isotopic Abundance 2.086 % 2247800200008 ENDBIB 6 0 2247800200009 NOCOMMON 0 0 2247800200010 DATA 3 6 2247800200011 EN DATA ERR-T 2247800200012 MEV MB MB 2247800200013 13.6 22.5 1.5 2247800200014 13.7 22.1 1.4 2247800200015 14.1 25.9 1.6 2247800200016 14.5 26.3 1.7 2247800200017 14.7 27.6 1.8 2247800200018 14.9 27.9 1.8 2247800200019 ENDDATA 8 0 2247800200020 ENDSUBENT 19 0 2247800299999 SUBENT 22478003 20010611 00002247800300001 BIB 3 6 2247800300002 REACTION (21-SC-45(N,A)19-K-42,,SIG) 2247800300003 DECAY-DATA (19-K-42,12.36HR,DG,1524.6,0.1808) 2247800300004 SAMPLE .Sample As a Disk Pellets 13 mm Diameter, 8.5 mm 2247800300005 Thickness Pressed from High-Purity (99.99%) Oxides 2247800300006 Sc2-O3, Weight 1.5 Gram, Sandwiched Between Two 1-Mm 2247800300007 Thick Aluminium Foils, Isotopic Abundance 100 % 2247800300008 ENDBIB 6 0 2247800300009 NOCOMMON 0 0 2247800300010 DATA 3 6 2247800300011 EN DATA ERR-T 2247800300012 MEV MB MB 2247800300013 13.6 55.4 4.3 2247800300014 13.7 56.4 4.3 2247800300015 14.1 61.8 4.8 2247800300016 14.5 58.2 4.5 2247800300017 14.7 59.7 4.6 2247800300018 14.9 56.2 4.3 2247800300019 ENDDATA 8 0 2247800300020 ENDSUBENT 19 0 2247800399999 SUBENT 22478004 20010611 00002247800400001 BIB 3 8 2247800400002 REACTION (23-V-51(N,A)21-SC-48,,SIG) 2247800400003 DECAY-DATA (21-SC-48,43.7HR,DG,983.5,1.000, 2247800400004 DG,1037.5,0.975, 2247800400005 DG,1312.1,1.00) 2247800400006 SAMPLE .Sample As a Disk Pellets 13 mm Diameter, 8.5 mm 2247800400007 Thickness Pressed from High-Purity (99.99%) Oxides 2247800400008 V2-O5 , Weight 1.5 Gram, Sandwiched Between Two 1-Mm 2247800400009 Thick Aluminium Foils, Isotopic Abundance 99.75 % 2247800400010 ENDBIB 8 0 2247800400011 NOCOMMON 0 0 2247800400012 DATA 3 6 2247800400013 EN DATA ERR-T 2247800400014 MEV MB MB 2247800400015 13.6 13.6 0.9 2247800400016 13.7 14.1 0.9 2247800400017 14.1 15.2 1. 2247800400018 14.5 16.3 1. 2247800400019 14.7 17.3 1.1 2247800400020 14.9 16.5 1. 2247800400021 ENDDATA 8 0 2247800400022 ENDSUBENT 21 0 2247800499999 ENDENTRY 4 0 2247899999999