ENTRY 22392 20020218 00002239200000001 SUBENT 22392001 20020218 00002239200100001 BIB 16 65 2239200100002 TITLE .Cross-Section Measurements For Short-Lived 2239200100003 Isotopes of 46Ti, 75As, 92Mo and 97Mo 2239200100004 At the Neutron Energies from 13.6 to 14.9 MeV 2239200100005 AUTHOR (E.GUELTEKIN,V.BOSTAN,M.N.ERDURAN,M.SUBASI,M.SIRIN) 2239200100006 INSTITUTE (2TUKCNA) Gueltekin, Cekmece Nucl Res. And Training 2239200100007 Center 2239200100008 (2TUKSTU) Bostan, Erduran, University of Istanbul 2239200100009 (2TUKYTU) Subashi, Sirin - Yildiz Technical University,2239200100010 Physics Department 2239200100011 REFERENCE (J,ANE,28,53,2001) Main Reference, Data are Given 2239200100012 For 46Ti, 75As, 92Mo 2239200100013 (C,97TRIEST,1,622,199705) Preliminary Data For 46Ti, 2239200100014 75As,92Mo,97Mo 2239200100015 (J,NSE,130,254,1998) Experimental Details 2239200100016 (J,NSE,122,423,1996) Experimental Details 2239200100017 FACILITY (LINAC,2TUKCNA) 'SAMES' T-400 Neutron Generator, 2239200100018 Average Deutron Beam Current 500 Microamp, 2239200100019 Accelerating Voltage 300 Kv 2239200100020 INC-SOURCE (D-T) For Short-Lived Isotopes Fast Sample Transfer 2239200100021 System was Used with Cyclic Activation Which 2239200100022 Deliveres Sample from Irradiation to Counting 2239200100023 Position Within 0.5 Sec 2239200100024 DETECTOR (HPGE) Coaxial, 83 Cm3 Volume, whithin 10 Cm-Thick 2239200100025 Lead Shield, 1.79 KeV Full Width at Half-Maximum2239200100026 At 1333 KeV Gamma Energy 2239200100027 (SCIN) For Neutron Flux Monitoring 2239200100028 METHOD (ACTIV) Activation 2239200100029 (TOF) Time-Of-Flight Supplied As the'Input Spectrum'2239200100030 INC-SPECT .Irradiation Positions are 0, 30, 60, 90, 120 and 130 2239200100031 Degrees Relative to Deutron Beam Which Correspond 2239200100032 To Neutron Energies 14.9, 14.7, 14.5, 14.1, 13.7, 2239200100033 13.6 MeV 2239200100034 .Mean Effective Neutron Energy at the Sample Position 2239200100035 Has Been Determined by the Ratio of 90Zr(N,2N)89Zr 2239200100036 And 93Nb(N,2N)92M-Nb Reactions Cross Sections 2239200100037 MONITOR (13-AL-27(N,P)12-MG-27,,SIG) 2239200100038 DECAY-MON (12-MG-27,9.42MIN,DG,844.) 2239200100039 SAMPLE .Round Pellets 13 mm in Diameter, 8.5 mm Thickness 2239200100040 Were Pressed from High-Purity Oxides and Packed in 2239200100041 Thin Polyethilene Capsules 2239200100042 .Aluminium Oxide Al2-O3 Pellets of the Same Size were 2239200100043 Used As Standard Cross Section Sample 2239200100044 CORRECTION .Corrections were Made For the Effect of Gamma Ray 2239200100045 Attenuation, Coincidence Summing, Pulse Pile-Up, 2239200100046 Dead Time of the Detector, Neutron Flux Fluctuation 2239200100047 And Scattered Neutrons 2239200100048 ADD-RES (THEO) Statistical Calculations of Cross-Sections 2239200100049 ERR-ANALYS (ERR-T) Total Error. Error Structure Given in Main 2239200100050 Reference 2239200100051 (ERR-1) Error in the Sample Weight 2239200100052 (ERR-2) Error in the Concentration of the Element 2239200100053 (ERR-3) Error in the Counting Solid Angle and 2239200100054 Intrinsic Efficiency of the Gamma Detector 2239200100055 (ERR-4) Max Error in Full Energy Photo-Peak Area 2239200100056 (ERR-5) Error in the Self-Absorption of Gamma Rays 2239200100057 (ERR-6) Max Error in Gamma-Gamma Coincidence Summing 2239200100058 (ERR-7) Error in Effective Neutron Flux 2239200100059 (ERR-8) Error Due to Neutron Flux Fluctuations 2239200100060 (ERR-9) Max Error Due to Low Energy Neutrons 2239200100061 (ERR-10) Error Due to Irradiation, Cooling and 2239200100062 Measuring Times 2239200100063 HISTORY (19980721C) + + Compiled by S.M. 2239200100064 (20020218A) Corrected by S.M. Bib-Information 2239200100065 Added from Main Reference 2239200100066 (20020218U) Last checking has been done. 2239200100067 ENDBIB 65 0 2239200100068 COMMON 10 6 2239200100069 ERR-1 ERR-2 ERR-3 ERR-4 ERR-5 ERR-6 2239200100070 ERR-7 ERR-8 ERR-9 ERR-10 2239200100071 PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT PER-CENT 2239200100072 PER-CENT PER-CENT PER-CENT PER-CENT 2239200100073 0.1 0.5 0.3 2. 0.2 4.2239200100074 3. 0.1 2. 0.1 2239200100075 ENDCOMMON 6 0 2239200100076 ENDSUBENT 75 0 2239200199999 SUBENT 22392002 20020218 00002239200200001 BIB 2 3 2239200200002 REACTION (22-TI-46(N,P)21-SC-46-M,,SIG) 2239200200003 STATUS . From Table 2 of Main Reference 2239200200004 (APRVD) 2239200200005 ENDBIB 3 0 2239200200006 NOCOMMON 0 0 2239200200007 DATA 4 6 2239200200008 EN EN-RSL DATA ERR-T 2239200200009 MEV MEV MB MB 2239200200010 13.6 0.8 48.3 2.45 2239200200011 13.68 0.81 48.81 2.57 2239200200012 14.1 0.1 46.17 2.42 2239200200013 14.46 0.11 49.03 2.56 2239200200014 14.72 0.11 44.64 2.54 2239200200015 14.86 0.12 45.38 2.38 2239200200016 ENDDATA 8 0 2239200200017 ENDSUBENT 16 0 2239200299999 SUBENT 22392003 20020218 00002239200300001 BIB 2 3 2239200300002 REACTION (33-AS-75(N,P)32-GE-75-M,,SIG) 2239200300003 STATUS . From Table 2 of Main Reference 2239200300004 (APRVD) 2239200300005 ENDBIB 3 0 2239200300006 NOCOMMON 0 0 2239200300007 DATA 4 6 2239200300008 EN EN-RSL DATA ERR-T 2239200300009 MEV MEV MB MB 2239200300010 13.6 0.8 12.67 0.72 2239200300011 13.68 0.81 11.42 0.72 2239200300012 14.1 0.1 11.58 0.73 2239200300013 14.46 0.11 11.77 0.74 2239200300014 14.72 0.11 11.84 0.75 2239200300015 14.86 0.12 10.37 0.65 2239200300016 ENDDATA 8 0 2239200300017 ENDSUBENT 16 0 2239200399999 SUBENT 22392004 20020218 00002239200400001 BIB 2 3 2239200400002 REACTION (42-MO-97(N,P)41-NB-97-M,,SIG) 2239200400003 STATUS . From Second Reference 2239200400004 (PRELM) 2239200400005 ENDBIB 3 0 2239200400006 NOCOMMON 0 0 2239200400007 DATA 4 6 2239200400008 EN EN-RSL DATA ERR-T 2239200400009 MEV MEV MB MB 2239200400010 13.6 0.8 3.25 0.3 2239200400011 13.68 0.81 3.28 0.32 2239200400012 14.1 0.1 4.13 0.41 2239200400013 14.46 0.11 5.97 0.6 2239200400014 14.72 0.11 6.29 0.63 2239200400015 14.86 0.12 5.6 0.55 2239200400016 ENDDATA 8 0 2239200400017 ENDSUBENT 16 0 2239200499999 SUBENT 22392005 20020218 00002239200500001 BIB 2 3 2239200500002 REACTION (42-MO-92(N,2N)42-MO-91-M,,SIG) 2239200500003 STATUS . From Table 2 of Main Reference 2239200500004 (APRVD) 2239200500005 ENDBIB 3 0 2239200500006 NOCOMMON 0 0 2239200500007 DATA 4 6 2239200500008 EN EN-RSL DATA ERR-T 2239200500009 MEV MEV MB MB 2239200500010 13.6 0.8 1.25 0.56 2239200500011 13.68 0.81 1.85 0.65 2239200500012 14.1 0.1 8.84 0.96 2239200500013 14.46 0.11 19.86 1.24 2239200500014 14.72 0.11 32.52 2.05 2239200500015 14.86 0.12 36.24 2.13 2239200500016 ENDDATA 8 0 2239200500017 ENDSUBENT 16 0 2239200599999 ENDENTRY 5 0 2239299999999