ENTRY 30497 20220217 32073049700000001 SUBENT 30497001 20220217 32073049700100001 BIB 14 47 3049700100002 TITLE Yields and energy spectra of light charged particles 3049700100003 emitted in neutron induced fission of 235U 3049700100004 AUTHOR (B.Krishnarajulu, G.K.Mehta, R.K.Choudhury, 3049700100005 D.M.Nadkarni, S.S.Kapoor) 3049700100006 INSTITUTE (3INDITK,3INDTRM) 3049700100007 REFERENCE (J,PRM,8,315,1977) 3049700100008 (P,BARC-978,56(2),1978) Graph available 3049700100009 (C,76AHMEDABA,2,112,1976) Graph available 3049700100010 FACILITY (VDG,3INDITK) 2 MeV Van de Graaff 3049700100011 INC-SOURCE Thermal neutrons were produced by placing a 5 cm 3049700100012 paraffine block in the neutron path. 3049700100013 (P-LI7) Neutron-energy spread about 40 keV. 3049700100014 (P-T) Neutron-energy spread about 160 keV. 3049700100015 The average fission rate ~2.5 X 10**3 sec-1 and 3049700100016 neutron flux was estimated about 5 X 10**7 n/cm2/sec. 3049700100017 SAMPLE A 235U target (5 mg/cm2 thick, ~4 cm2 area). 3049700100018 DETECTOR (IOCH) Filled with high purity argon, pressure of 3049700100019 1.1 atm. 3049700100020 (SIBAR) Surface-barrier, depletion depth 400 um, 3049700100021 mounted inside the ionization chamber to detect the 3049700100022 light charged particles ('LCP'). 3049700100023 METHOD The natural alphas and the fission fragments were 3049700100024 stopped in an aluminum foil before reaching the 3049700100025 LCP-detector. 3049700100026 (COINC) After each coinc- run, ungated LCP-spectra 3049700100027 were recorded in order to determine chance 3049700100028 coincidences. Before and after each fast-neutron run, 3049700100029 thermal runs were performed to check the detector 3049700100030 performance and for normalization of the LCP-spectra. 3049700100031 ANALYSIS A Gaussian was fitted by least squares method to the 3049700100032 measured spectra beyond 12 MeV. The LCP-yields above 3049700100033 12 MeV were attributed to alpha-particles alone. 3049700100034 The difference between measured spectra from 6.5 to 3049700100035 12 MeV and Gaussian was assumed to be due to tritons. 3049700100036 The quoted alpha and triton yields relative to thermal 3049700100037 were obtained through this assumption. 3049700100038 CORRECTION The observed spectra were corrected for chance coinc., 3049700100039 then for energy losses in the source, gas and aluminium3049700100040 foil. 3049700100041 ERR-ANALYS (DATA-ERR) No information on source of uncertainties. 3049700100042 STATUS (TABLE) Fig. 3(a-b) of Pramana,8(1977)315 3049700100043 The numerical data were communicated from G.K.Mehta. 3049700100044 HISTORY (19790712C) TL. 3049700100045 (20090312A) SD: Updated to new date formats,lower case.3049700100046 (20100303A) SD: REACTION code in Subent 002 was changed3049700100047 according to EXFOR rules. 3049700100048 (20220217A) VT Revision in 002,REFERENCE:BARC,56->56(2)3049700100049 ENDBIB 47 0 3049700100050 NOCOMMON 0 0 3049700100051 ENDSUBENT 50 0 3049700199999 SUBENT 30497002 20220217 32073049700200001 BIB 6 10 3049700200002 REACTION (92-U-235(N,F)2-HE-4,TER,KE) 3049700200003 SAMPLE (92-U-235,ENR=0.939) 3049700200004 MONITOR (92-U-235(N,F)2-HE-4,TER,KE,,MXW) 3049700200005 Low intensity 241Am and 237Np sources were used for 3049700200006 energy calibration. 3049700200007 MISC-COL (MISC) Half width at half maximum of fitted gaussian. 3049700200008 ANALYSIS Maximum of fitted Gaussian 3049700200009 HISTORY (20100303A) SD: REACTION code was changed 3049700200010 according to EXFOR rules. 3049700200011 (20220217A) VT MONITOR:SF4->2-HE-4 added,SF7->A deleted3049700200012 ENDBIB 10 0 3049700200013 COMMON 3 3 3049700200014 MONIT MONIT-ERR EN-NRM 3049700200015 MEV MEV EV 3049700200016 15.0 0.1 2.53E-2 3049700200017 ENDCOMMON 3 0 3049700200018 DATA 6 6 3049700200019 EN EN-RSL DATA DATA-ERR MISC MISC-ERR 3049700200020 KEV KEV MEV MEV MEV MEV 3049700200021 2.53E-5 15.0 0.1 4.87 0.123049700200022 120. 40. 15.10 0.09 5.09 0.153049700200023 180. 40. 14.30 0.06 4.56 0.113049700200024 500. 180. 15.66 0.10 4.72 0.193049700200025 800. 180. 15.06 0.10 4.38 0.163049700200026 1020. 180. 15.16 0.08 5.41 0.133049700200027 ENDDATA 8 0 3049700200028 ENDSUBENT 27 0 3049700299999 ENDENTRY 2 0 3049799999999