ENTRY 22474 20010611 00002247400000001 SUBENT 22474001 20010611 00002247400100001 BIB 17 59 2247400100002 TITLE .Measurement of 50Ti(N,ALPHA)47Ca Reaction Cross 2247400100003 Sections For 13.6 - To 14.9 MeV Neutrons 2247400100004 AUTHOR (M.SUBASI, M.BOSTAN, M.N.ERDURAN, A.DURUSOY, 2247400100005 E.GUELTEKIN, G.TARCAN, Y.OZBIR) 2247400100006 INSTITUTE (2TUKCNA) Subasi, Gueltekin, Ozbir, Bostan, Erduran, 2247400100007 Tarkan 2247400100008 (2TUKYTU) Durusoy 2247400100009 REFERENCE (J,NSE,122,423,1996) Main Reference 2247400100010 METHOD (ACTIV) Activation 2247400100011 (STTA) Stack Target Sample with Aluminium Backings 2247400100012 In Front and at the Rear of the Sample 2247400100013 PART-DET (G) 2247400100014 DETECTOR (HPGE) Coaxial Detector 'Canberra', Volume 82 Cm3 with 2247400100015 1.79 KeV Full Width at Half-Maximum at 1333 KeV 2247400100016 Gamma-Energy 2247400100017 FACILITY (LINAC,2TUKCNA) .Neutron Generator 'SAMES T-400' 2247400100018 Voltage is 300 Kv, Average Beam Current 500 Mucro-A 2247400100019 MONITOR (13-AL-27(N,A)11-NA-24,,SIG) 2247400100020 (40-ZR-90(N,2N)40-ZR-89,,SIG) 2247400100021 (41-NB-93(N,2N)41-NB-92-M,,SIG) 2247400100022 DECAY-MON (11-NA-24,14.959HR,DG,1369.) 2247400100023 (40-ZR-89,78.41HR,DG) 2247400100024 (41-NB-92-M,10.15D,DG) 2247400100025 MONIT-REF (,R.KINSEY,R,ENDF-201,1979) 2247400100026 INC-SOURCE (D-T) 2247400100027 INC-SPECT .Angles of Irradiation of the Target by Deuteruim Ion 2247400100028 Beam are 0, 30, 60, 90, 120 and 130 Degrees. Effective2247400100029 Mean Neutron Energy at Each Sample Position had Been 2247400100030 Previously Determined by the Ratio of 90Zr(N,2N)89Zr 2247400100031 And 93Nb(N,2N)92M-Nb Cross Sections 2247400100032 .Neutron Fluxes Ranged from 1.E+7 to 6.E+7 N/Cm2/Sec 2247400100033 SAMPLE .Disk Pellets 13 mm Diameter, 8.5 mm Thicknesss 2247400100034 Pressed from the Natural High-Purity (99.9%) Oxides 2247400100035 Ti-O2, Weight 2.6 Gram, Sandwiched Between Two 1-Mm 2247400100036 Thick Aluminium Foils, and Al2-O3 Sample of the Same 2247400100037 Arrangment. 2247400100038 CORRECTION .Corrections were Made For Self-Absorption of Gamma in 2247400100039 Samples and For Neutron Flux Attenuation Using the 2247400100040 Activity Difference Between the Front and Back Alumi- 2247400100041 Nium Foils, For Coincidence Summing, Ghamma-Ray 2247400100042 Attenuation in the Sample 2247400100043 ERR-ANALYS (ERR-T) Total Error 2247400100044 (ERR-1) Error of the Sample Weight 2247400100045 (ERR-2) Error Due to Concentration of the Elements 2247400100046 In Samples 2247400100047 (ERR-3) Error Due to Isotopic Abundance 2247400100048 (ERR-4) Error Due to Relative Gamma-Ray Intensity 2247400100049 (ERR-5) Error Due to the Efficiency of Gamma Detector 2247400100050 And Due to Counting Solid Angle 2247400100051 (ERR-6) Max Error Due to Full-Energy Photo-Peak Area 2247400100052 (ERR-7) Min Error Due to Full-Energy Photo-Peak Area 2247400100053 (ERR-8) Error Due to Neutron Flux Fluctuations Inclu- 2247400100054 Ding Uncertainty of the Reference Cross- 2247400100055 Section 2247400100056 (ERR-9) Error of Irradiation, Cooling and Measuring 2247400100057 Time 2247400100058 (ERR-10) Error of the Half-Life of the Active Nuclei 2247400100059 HISTORY (20010611C) + + Compiled by S.M. 2247400100060 (20010611U) Last checking has been done. 2247400100061 ENDBIB 59 0 2247400100062 COMMON 10 6 2247400100063 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2247400100064 ERR-7 ERR-8 ERR-9 ERR-10 2247400100065 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2247400100066 PER-CENT PER-CENT PER-CENT PER-CENT 2247400100067 0.1 0.5 0.1 2.5 3. 9.92247400100068 4.6 3. 0.1 0.1 2247400100069 ENDCOMMON 6 0 2247400100070 ENDSUBENT 69 0 2247400199999 SUBENT 22474002 20010611 00002247400200001 BIB 2 2 2247400200002 REACTION (22-TI-50(N,A)20-CA-47,,SIG) 2247400200003 DECAY-DATA (20-CA-47,4.536D,DG) 2247400200004 ENDBIB 2 0 2247400200005 NOCOMMON 0 0 2247400200006 DATA 3 6 2247400200007 EN DATA ERR-T 2247400200008 MEV MB MB 2247400200009 13.6 6.41 .68 2247400200010 13.68 6.54 .72 2247400200011 14.1 7.55 .73 2247400200012 14.46 8.37 .75 2247400200013 14.72 9.22 .61 2247400200014 14.86 9.8 .98 2247400200015 ENDDATA 8 0 2247400200016 ENDSUBENT 15 0 2247400299999 ENDENTRY 2 0 2247499999999