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