ENTRY 31564 20051214 31183156400000001 SUBENT 31564001 20051214 31183156400100001 BIB 17 60 3156400100002 TITLE Measurement of fission neutron spectrum averaged cross 3156400100003 sections of some threshold reactions on ruthenium: 3156400100004 small scale production of 96Tc in a nuclear reactor 3156400100005 AUTHOR (M.Arif,J.H.Zaidi,I.H.Qureshi,M.Zafar Iqbal) 3156400100006 REFERENCE (J,RCA,85,9,1999) 3156400100007 INSTITUTE (3PAKNIL) 3156400100008 (3PAKPAK) University of the Punjab, Lahore, Pakistan 3156400100009 FACILITY (REAC,3PAKNIL) 5 MW swimming pool type Pakistan 3156400100010 research reactor ( PARR-I) at Pinstech. 3156400100011 SAMPLE High purity ruthenium sponge (99.999% pure), weighing 3156400100012 25-50 mg, was filled in a quartz ampoule, sealed and 3156400100013 then placed in an NRX type irradiation capsule. Two of 3156400100014 each of the three neutron flux monitor foils (Au, Fe 3156400100015 and Ni), were placed in a cylindrical arrangement 3156400100016 around the ampoule in such a way that the same neutron 3156400100017 flux monitor material was on opposite sides of the 3156400100018 ampoule, allowing thereby a determination of the 3156400100019 effective flux density within the ampoule. 3156400100020 The foils were washed with acetone; dried and weighed 3156400100021 before attaching to the ampoules. 3156400100022 MONITOR ((MONIT1)26-FE-54(N,P)25-MN-54,,SIG,,FIS) 3156400100023 ((MONIT2)26-FE-56(N,P)25-MN-56,,SIG,,FIS) 3156400100024 ((MONIT3)28-NI-58(N,P)27-CO-58,,SIG,,FIS) 3156400100025 ((MONIT4)28-NI-60(N,P)27-CO-60,,SIG,,FIS) 3156400100026 MONIT-REF (,A.CALAMAND,R,IAEA-156,273,1974) First four monitor 3156400100027 reactions. 3156400100028 INC-SPECT From measurement of the fast/thermal -neutron flux 3156400100029 ratio for monitor reactions having different threshold 3156400100030 it was concluded that the neutron spectrum used was 3156400100031 approximately a fission spectrum. 3156400100032 INC-SOURCE (REAC) 3156400100033 METHOD (ACTIV,GSPEC) Cross sections were measured by neutron 3156400100034 activation of the target nuclei and the radioactive 3156400100035 products were identified by gamma-ray spectrometry. 3156400100036 (CHSEP) A new radiochemical separation was proposed. 3156400100037 Tracer experiments showed the chemical yield of the 3156400100038 procedure up to 98 +- 2%. 3156400100039 DETECTOR (GELI) The radioactivity of the reaction products and 3156400100040 the monitor reactions was determined by gamma-ray 3156400100041 spectrometry using a coaxial 30 cm3 Ge(Li) detector in 3156400100042 conjunction with a 4 K Canberra Series 85 multichannel 3156400100043 analyzer. 3156400100044 PART-DET (DG) 3156400100045 CORRECTION In converting the count rates to decay rates correc- 3156400100046 tions were applied for radiochemical yields, gamma-ray 3156400100047 intensities, detector efficiencies, counting geometry, 3156400100048 absorption, self-absorption, pile-up effects and 3156400100049 coincidence losses. 3156400100050 ERR-ANALYS (ERR-T) The reported uncertainties incorporate both 3156400100051 statistical and systematic errors. Main sources of 3156400100052 errors associated in cross-section measurements were 3156400100053 those associated with determination of fast neutron 3156400100054 flux densities (8%) and absolute decay rates (5 to 10%)3156400100055 Other sources of error were small and were due to 3156400100056 uncertainties in the number of target nuclei < 1% and 3156400100057 in radiation and cooling times ( 1%). 3156400100058 Entry aprroved by Dr. Jamshed Hussain Zaidi 3156400100059 STATUS (TABLE) Data taken from Tabl.2 of main reference. 3156400100060 (APRVD) Entry aprroved by Dr. Jamshed Hussain Zaidi 3156400100061 HISTORY (20051214C) SD 3156400100062 ENDBIB 60 0 3156400100063 COMMON 9 6 3156400100064 EN-DUMMY MONIT1 MONIT1-ERR MONIT2 MONIT2-ERR MONIT3 3156400100065 MONIT3-ERR MONIT4 MONIT4-ERR 3156400100066 MEV MB MB MB MB MB 3156400100067 MB B B 3156400100068 1.5 82.5 5.0 1.07 .08 113. 3156400100069 7.0 2.3 0.4 3156400100070 ENDCOMMON 6 0 3156400100071 ENDSUBENT 70 0 3156400199999 SUBENT 31564002 20051214 31183156400200001 BIB 2 3 3156400200002 REACTION (44-RU-96(N,P)43-TC-96,,SIG,,FIS) 3156400200003 DECAY-DATA (43-TC-96-G,4.28D,DG,778.2,0.9976,DG,1200.5,0.0037) 3156400200004 (43-TC-96-M,51.5MIN) 3156400200005 ENDBIB 3 0 3156400200006 NOCOMMON 0 0 3156400200007 DATA 2 1 3156400200008 DATA ERR-T 3156400200009 MB MB 3156400200010 8.4 1.1 3156400200011 ENDDATA 3 0 3156400200012 ENDSUBENT 11 0 3156400299999 SUBENT 31564003 20051214 31183156400300001 BIB 1 1 3156400300002 REACTION (44-RU-96(N,2N)44-RU-95,,SIG,,FIS) 3156400300003 ENDBIB 1 0 3156400300004 NOCOMMON 0 0 3156400300005 DATA 2 1 3156400300006 DATA ERR-T 3156400300007 MB MB 3156400300008 0.31 0.06 3156400300009 ENDDATA 3 0 3156400300010 ENDSUBENT 9 0 3156400399999 SUBENT 31564004 20051214 31183156400400001 BIB 1 1 3156400400002 REACTION (44-RU-96(N,A)42-MO-93-M,,SIG,,FIS) 3156400400003 ENDBIB 1 0 3156400400004 NOCOMMON 0 0 3156400400005 DATA 2 1 3156400400006 DATA ERR-T 3156400400007 MB MB 3156400400008 1.8 0.3 3156400400009 ENDDATA 3 0 3156400400010 ENDSUBENT 9 0 3156400499999 SUBENT 31564005 20051214 31183156400500001 BIB 2 2 3156400500002 REACTION (44-RU-99(N,P)43-TC-99-M,,SIG,,FIS) 3156400500003 DECAY-DATA (43-TC-99-M,6.HR) 3156400500004 ENDBIB 2 0 3156400500005 NOCOMMON 0 0 3156400500006 DATA 2 1 3156400500007 DATA ERR-T 3156400500008 MB MB 3156400500009 0.34 0.06 3156400500010 ENDDATA 3 0 3156400500011 ENDSUBENT 10 0 3156400599999 SUBENT 31564006 20051214 31183156400600001 BIB 2 2 3156400600002 REACTION (44-RU-101(N,P)43-TC-101,,SIG,,FIS) 3156400600003 DECAY-DATA (43-TC-101,14.2MIN) 3156400600004 ENDBIB 2 0 3156400600005 NOCOMMON 0 0 3156400600006 DATA 2 1 3156400600007 DATA ERR-T 3156400600008 MB MB 3156400600009 1.2 0.2 3156400600010 ENDDATA 3 0 3156400600011 ENDSUBENT 10 0 3156400699999 SUBENT 31564007 20051214 31183156400700001 BIB 1 1 3156400700002 REACTION (44-RU-102(N,A)42-MO-99,,SIG,,FIS) 3156400700003 ENDBIB 1 0 3156400700004 NOCOMMON 0 0 3156400700005 DATA 2 1 3156400700006 DATA ERR-T 3156400700007 MB MB 3156400700008 0.06 0.01 3156400700009 ENDDATA 3 0 3156400700010 ENDSUBENT 9 0 3156400799999 SUBENT 31564008 20051214 31183156400800001 BIB 2 2 3156400800002 REACTION (44-RU-104(N,P)43-TC-104,,SIG,,FIS) 3156400800003 DECAY-DATA (43-TC-104,18.3MIN) 3156400800004 ENDBIB 2 0 3156400800005 NOCOMMON 0 0 3156400800006 DATA 2 1 3156400800007 DATA ERR-T 3156400800008 MB MB 3156400800009 0.55 0.10 3156400800010 ENDDATA 3 0 3156400800011 ENDSUBENT 10 0 3156400899999 SUBENT 31564009 20051214 31183156400900001 BIB 1 1 3156400900002 REACTION (44-RU-104(N,A)42-MO-101,,SIG,,FIS) 3156400900003 ENDBIB 1 0 3156400900004 NOCOMMON 0 0 3156400900005 DATA 2 1 3156400900006 DATA ERR-T 3156400900007 MB MB 3156400900008 0.04 0.001 3156400900009 ENDDATA 3 0 3156400900010 ENDSUBENT 9 0 3156400999999 ENDENTRY 9 0 3156499999999