ENTRY 31561 20130701 31603156100000001 SUBENT 31561001 20130701 31603156100100001 BIB 18 59 3156100100002 TITLE Fission neutron spectrum averaged cross sections of 3156100100003 some threshold reactions on titanium: production 3156100100004 feasibility of 45Ti in a nuclear reactor 3156100100005 AUTHOR (I.Fatima, J.H.Zaidi, I.H.Qureshi, M.S.Subhami) 3156100100006 REFERENCE (J,RCA,90,123,2002) 3156100100007 INSTITUTE (3PAKNIL) 3156100100008 (3PAKPAK) Quaid-e-Azam University, Islamabad 3156100100009 FACILITY (REAC,3PAKNIL) 5 MW swimming pool type Pakistan 3156100100010 research reactor (PARR-I) at Pinstech. 3156100100011 SAMPLE High purity titanium sponge (99.999% pure), weighing 3156100100012 25-50 mg, was filled in a quartz ampoule, sealed and 3156100100013 then placed in an NRX type aluminum irradiation 3156100100014 capsule. 3156100100015 Two of each of the three neutron flux monitor foils 3156100100016 (Au, Fe and Ni) were placed in a cylindrical 3156100100017 arrangement around the ampoule in such a way that the 3156100100018 same neutron flux monitor material was on opposite 3156100100019 sides of the ampoule, allowing thereby a 3156100100020 determination of the effective flux density within 3156100100021 the ampoule. 3156100100022 The foils were washed with acetone; dried and weighed 3156100100023 before attaching to the ampoules. 3156100100024 MONITOR ((MONIT1)26-FE-54(N,P)25-MN-54,,SIG,,FIS) 3156100100025 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG,,FIS) 3156100100026 ((MONIT3)28-NI-58(N,P)27-CO-58,,SIG,,FIS) 3156100100027 ((MONIT4)28-NI-60(N,P)27-CO-60,,SIG,,FIS) 3156100100028 MONIT-REF (,A.Calamand,R,IAEA-156,273,1974) 3156100100029 INC-SPECT From measurement of the fast/thermal -neutron flux 3156100100030 ratio for monitor reactions having different 3156100100031 threshold it was concluded that the neutron spectrum 3156100100032 used was approximately a fission spectrum. 3156100100033 INC-SOURCE (REAC) 3156100100034 METHOD (ACTIV,GSPEC) Cross sections were measured by neutron 3156100100035 activation of the target nuclei and the radioactive 3156100100036 products were identified by gamma-ray spectrometry. 3156100100037 (CHSEP) Tracer experiments showed the chemical yield 3156100100038 of the procedure up to 98 +/- 2%. 3156100100039 DETECTOR (GELI) The radioactivity of the reaction products and 3156100100040 the monitor reactions was determined by gamma-ray 3156100100041 spectrometry using a coaxial 30 cm3 Ge(Li) detector 3156100100042 in conjunction with a 4 K Canberra Series 85 3156100100043 multichannel analyzer. 3156100100044 PART-DET (DG) 3156100100045 CORRECTION In converting the count rates to decay rates 3156100100046 corrections were applied for radiochemical yields, 3156100100047 gamma-ray intensities, detector efficiencies, 3156100100048 counting geometry, absorption, self-absorption, pile- 3156100100049 up effects and coincidence losses. 3156100100050 ERR-ANALYS (ERR-T) The reported uncertainties incorporate both 3156100100051 statistical and systematic errors. 3156100100052 (ERR-1) Fast neutron flux densities (8%) 3156100100053 (ERR-2) Radiation and cooling times (1%) 3156100100054 (ERR-3,5.,10.) Absolute decay rates (5-10%) 3156100100055 (ERR-4,,1.) Number of target nuclei (<1%) 3156100100056 DECAY-DATA No information was given about decay data. 3156100100057 STATUS (TABLE) Table 2 of Radiochim.Acta.90(2002)123 3156100100058 (APRVD) Entry approved by Dr. Jamshed Hussain Zaidi 3156100100059 HISTORY (20051214C) SD 3156100100060 (20130701A) On. MONIT4(-ERR): B -> MB, ERR-1, -2 added 3156100100061 ENDBIB 59 0 3156100100062 COMMON 11 6 3156100100063 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR MONIT3 3156100100064 MONIT3-ERR MONIT4 MONIT4-ERR ERR-1 ERR-2 3156100100065 MEV MB MB MB MB MB 3156100100066 MB MB MB PER-CENT PER-CENT 3156100100067 1.5 82.5 5.0 1.07 0.08 113. 3156100100068 7.0 2.3 0.4 8. 1. 3156100100069 ENDCOMMON 6 0 3156100100070 ENDSUBENT 69 0 3156100199999 SUBENT 31561002 20051214 31183156100200001 BIB 1 3 3156100200002 REACTION (22-TI-46(N,2N)22-TI-45,,SIG,,FIS) In the case of this 3156100200003 reaction, the contribution of the 5OTi(n,a)47Ca -> 47SC3156100200004 process was taken into account. 3156100200005 ENDBIB 3 0 3156100200006 NOCOMMON 0 0 3156100200007 DATA 2 1 3156100200008 DATA ERR-T 3156100200009 MICRO-B MICRO-B 3156100200010 4.57 0.5 3156100200011 ENDDATA 3 0 3156100200012 ENDSUBENT 11 0 3156100299999 SUBENT 31561003 20051214 31183156100300001 BIB 1 1 3156100300002 REACTION (22-TI-46(N,P)21-SC-46,,SIG,,FIS) 3156100300003 ENDBIB 1 0 3156100300004 NOCOMMON 0 0 3156100300005 DATA 2 1 3156100300006 DATA ERR-T 3156100300007 MB MB 3156100300008 12.87 1.28 3156100300009 ENDDATA 3 0 3156100300010 ENDSUBENT 9 0 3156100399999 SUBENT 31561004 20051214 31183156100400001 BIB 1 1 3156100400002 REACTION (22-TI-47(N,P)21-SC-47,,SIG,,FIS) 3156100400003 ENDBIB 1 0 3156100400004 NOCOMMON 0 0 3156100400005 DATA 2 1 3156100400006 DATA ERR-T 3156100400007 MB MB 3156100400008 20.11 2.02 3156100400009 ENDDATA 3 0 3156100400010 ENDSUBENT 9 0 3156100499999 SUBENT 31561005 20051214 31183156100500001 BIB 1 1 3156100500002 REACTION (22-TI-48(N,P)21-SC-48,,SIG,,FIS) 3156100500003 ENDBIB 1 0 3156100500004 NOCOMMON 0 0 3156100500005 DATA 2 1 3156100500006 DATA ERR-T 3156100500007 MB MB 3156100500008 0.32 0.04 3156100500009 ENDDATA 3 0 3156100500010 ENDSUBENT 9 0 3156100599999 SUBENT 31561006 20051214 31183156100600001 BIB 1 1 3156100600002 REACTION (22-TI-49(N,P)21-SC-49,,SIG,,FIS) 3156100600003 ENDBIB 1 0 3156100600004 NOCOMMON 0 0 3156100600005 DATA 2 1 3156100600006 DATA ERR-T 3156100600007 MB MB 3156100600008 27.05 2.43 3156100600009 ENDDATA 3 0 3156100600010 ENDSUBENT 9 0 3156100699999 SUBENT 31561007 20051214 31183156100700001 BIB 1 1 3156100700002 REACTION (22-TI-50(N,A)20-CA-47,,SIG,,FIS) 3156100700003 ENDBIB 1 0 3156100700004 NOCOMMON 0 0 3156100700005 DATA 2 1 3156100700006 DATA ERR-T 3156100700007 MB MB 3156100700008 4.49 0.45 3156100700009 ENDDATA 3 0 3156100700010 ENDSUBENT 9 0 3156100799999 ENDENTRY 7 0 3156199999999