ENTRY 33036 20110807 31553303600000001 SUBENT 33036001 20110807 31553303600100001 BIB 14 52 3303600100002 TITLE 233Pa(2nth f) cross-section determination using a 3303600100003 fission track technique 3303600100004 AUTHOR (H.Naik, P.M.Prajapati, S.V.Suryanarayana, P.N.Pathak, 3303600100005 D.R.Prabhu, V.Chavan, D.Raj, P.C.Kalsi, A.Goswami) 3303600100006 INSTITUTE (3INDTRM) 3303600100007 REFERENCE (J,EPJ/A,47,100,2011) 3303600100008 REL-REF (R,,S.F.Mughabghab,J,EPJ/A,47,100,2011) 3303600100009 FACILITY (REAC,3INDTRM) 3303600100010 INC-SOURCE (REAC)The neutron flux was estimated from the peak 3303600100011 area of the 411.8 keV of the flux monitor 198-Au. 3303600100012 SAMPLE About 6 g of thorium nitrate salt was wrapped with 3303600100013 0.025 mm thick aluminum foil and doubly sealed with 3303600100014 alkathene.5.2 ng of separated 233-Pa in the form of 3303600100015 nitrate was dried on a 0.025 mm thick aluminum foil. 3303600100016 Dried 233-Pa(NO3)3 was covered with a 0.0075 mm thick 3303600100017 Lexan foil of size 1.5 cm x 1.5 cm.233-Pa was 3303600100018 prepared from activation of 232-Th followed by beta 3303600100019 decay. 3303600100020 Di-isobutyl carbinol (DIBC), procured from Aldrich, 3303600100021 USA, was used as an extractant for the radiochemical 3303600100022 separation of 233-Pa and quantitative stripping was 3303600100023 achieved by 0.1 N HCl. 3303600100024 The amount of 233-Pa was estimated using gamma-ray 3303600100025 (311.9 keV) spectrometric technique and decay 3303600100026 equation. 3303600100027 DETECTOR (HPGE,TRD) The Purity and amount of the 233-Pa was 3303600100028 ascertained by a gamma-ray spectrometric technique 3303600100029 using an energy and efficiency calibrated 80 cm3 HPGe 3303600100030 detector coupled to a PC-based 4K channel 3303600100031 analyzer. 3303600100032 The gamma-ray counting of the irradiated gold target 3303600100033 (flux monitor) was also done for the 411.8 keV gamma- 3303600100034 line of 198-Au using same 80 cm3 HPGe detector 3303600100035 coupled to the PC-based 4K-channel analyzer. 3303600100036 The counting of fission tracks in lexan foil within a 3303600100037 few fields i.e. fraction of the total area was done 3303600100038 by visual inspection under the microscope. 3303600100039 METHOD (ACTIV,RCHEM,GSPEC) 3303600100040 ANALYSIS The fission track in the lexan was counted manually 3303600100041 using optical microscope. 3303600100042 The 233-Pa(2nth,f)fission cross-section was calculated 3303600100043 from the fission track using tack density equation. 3303600100044 ERR-ANALYS (ERR-SYS) Total systematic uncertainty (1.8%) 3303600100045 (ERR-1) Replicate measurements (1.2%) 3303600100046 (ERR-2) Neutron flux (0.5%) 3303600100047 (ERR-3) Irradiation time (0.2%) 3303600100048 (ERR-4) Counting of fission track by microscope (1%) 3303600100049 STATUS (APRVD) Entry approved by Dr.H.Naik 3303600100050 HISTORY (20081111C) Dr.H.Naik of Radiochemistry Division of 3303600100051 B.A.R.C, Mumbai and Mr..Paresh M Prajapati of The M.S.3303600100052 University of Baroda, Vadodara 3303600100053 (20120430U) On. Finalized 3303600100054 ENDBIB 52 0 3303600100055 COMMON 5 3 3303600100056 EN ERR-1 ERR-2 ERR-3 ERR-4 3303600100057 EV PER-CENT PER-CENT PER-CENT PER-CENT 3303600100058 0.0253 1.2 0.5 0.2 1. 3303600100059 ENDCOMMON 3 0 3303600100060 ENDSUBENT 59 0 3303600199999 SUBENT 33036002 20110807 31553303600200001 BIB 4 4 3303600200002 REACTION (91-PA-234(N,F),,SIG) 3303600200003 MONITOR ((MONIT)79-AU-197(N,G)79-AU-198,,SIG) 3303600200004 DECAY-MON (79-AU-198,2.69517D,DG,411.80205,0.96963) 3303600200005 ASSUMED (ASSUM,91-PA-233(N,G)91-PA-234,,SIG) 3303600200006 ENDBIB 4 0 3303600200007 NOCOMMON 0 0 3303600200008 DATA 4 1 3303600200009 DATA ERR-SYS ASSUM MONIT 3303600200010 B PER-CENT B B 3303600200011 4834. 1.8 39.5 98.65 3303600200012 ENDDATA 3 0 3303600200013 ENDSUBENT 12 0 3303600299999 ENDENTRY 2 0 3303699999999