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