ENTRY 22824 20130110 22342282400000001
SUBENT 22824001 20130110 22342282400100001
BIB 19 51 2282400100002
TITLE .Measurements and statistical model calculations of 2282400100003
activation cross sections for 19-F(n,p)19-O reaction 2282400100004
between 13.6 and 14.9 MeV neutron energies 2282400100005
AUTHOR (I.A.Reyhancan) 2282400100006
INSTITUTE (2TUKCNA) 2282400100007
REFERENCE (J,ANE,30,1001,2003) Main reference, data given 2282400100008
REL-REF (M,22478001,M.Subasi+,J,NSE,130,254,1998) Experimental2282400100009
details 2282400100010
METHOD (ACTIV) Activation 2282400100011
(STTA) Stack target sample with aluminium backings 2282400100012
in front and at the rear of the sample 2282400100013
PART-DET (G) 2282400100014
DETECTOR (HPGE) Coaxial detector 'CANBERRA', volume 82 cm3 with 2282400100015
1.79 keV full width at half-maximum at 1333 keV 2282400100016
gamma-energy 2282400100017
FACILITY (VDG,2TUKCNA) Neutron generator 'SAMES T-400'. 2282400100018
Terminal voltage is 300 KV, average beam current 500 2282400100019
micro-Amperes 2282400100020
MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 2282400100021
DECAY-MON (12-MG-27,9.458MIN,DG,843.8,0.73) 2282400100022
MONIT-REF (41240002,A.Filatenkov+,R,INDC(CCP)-402,1997) 2282400100023
INC-SOURCE (D-T) 2282400100024
INC-SPECT .Angles of irradiation of the target by deuterium ion 2282400100025
beam are 0, 30, 60, 90, 120 and 130 degrees. Effective2282400100026
mean neutron energy at each sample position had been 2282400100027
previously determined by the ratio of 90Zr(n,2n)89Zr 2282400100028
and 93Nb(n,2n)92m-Nb cross sections 2282400100029
.Neutron fluxes ranged from 1.E+7 to 6.E+7 n/cm2/sec 2282400100030
SAMPLE .Model sample as a disk pellets 13 mm diameter, 8.5 mm 2282400100031
thickness made of pure teflon C2-F5, weight 2.9586 gr 2282400100032
CORRECTION .Corrections were made for gamma-ray attenuation in 2282400100033
samples, random coincidence, dead time and 2282400100034
fluctuation of neutron flux 2282400100035
ADD-RES (THEO) Statistical model calculation 2282400100036
ERR-ANALYS (ERR-T) Total error 2282400100037
(ERR-S) Statistical error of gamma-ray photo-peak area2282400100038
(ERR-1) Error of the sample weight 2282400100039
(ERR-2) Error due to concentration of the elements 2282400100040
in samples 2282400100041
(ERR-3) Error due to relative gamma-ray intensity 2282400100042
(ERR-4) Error due to the efficiency of gamma detector 2282400100043
and due to counting solid angle 2282400100044
(ERR-5) Error due to neutron flux fluctuations 2282400100045
(ERR-6) Error of irradiation, cooling and measuring 2282400100046
times 2282400100047
(ERR-7) Error due to gamma-gamma coincidence summing 2282400100048
(ERR-8) Error due to low energy neutrons 2282400100049
(ERR-9) Error due to self-absorption of gamma-rays 2282400100050
HISTORY (20010611C) + + J.O.S. 2282400100051
(20040128U) Last checking has been done. 2282400100052
(20130110U) SD: Facility was corrected (LINAC -> VDG) 2282400100053
ENDBIB 51 0 2282400100054
COMMON 11 6 2282400100055
ERR-S ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 2282400100056
ERR-6 ERR-7 ERR-8 ERR-9 MONIT-ERR 2282400100057
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2282400100058
PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2282400100059
0.35 0.1 0.5 0.3 0.3 0.1 2282400100060
0.1 3. 3. 0.2 3. 2282400100061
ENDCOMMON 6 0 2282400100062
ENDSUBENT 61 0 2282400199999
SUBENT 22824002 20040128 00002282400200001
BIB 3 4 2282400200002
REACTION (9-F-19(N,P)8-O-19,,SIG) 2282400200003
DECAY-DATA (8-O-19,26.91SEC,DG,197.14,0.959) 2282400200004
ERR-ANALYS (ERR-HL) Error of the half-life 2282400200005
(ERR-IDD) Error of the intensity 2282400200006
ENDBIB 4 0 2282400200007
COMMON 2 3 2282400200008
ERR-HL ERR-IDD 2282400200009
SEC PER-CENT 2282400200010
0.08 0.3 2282400200011
ENDCOMMON 3 0 2282400200012
DATA 4 6 2282400200013
EN DATA ERR-T MONIT 2282400200014
MEV MB MB MB 2282400200015
14.86 17.92 0.94 76.10 2282400200016
14.72 18.43 0.97 73.83 2282400200017
14.46 19.21 1.01 70.67 2282400200018
14.10 18.72 0.98 67.92 2282400200019
13.68 20.64 1.09 64.61 2282400200020
13.60 17.57 0.92 61.91 2282400200021
ENDDATA 8 0 2282400200022
ENDSUBENT 21 0 2282400299999
ENDENTRY 2 0 2282499999999