ENTRY 30498 20211108 32033049800000001 SUBENT 30498001 20211108 32033049800100001 BIB 14 45 3049800100002 INSTITUTE (3INDITK) 3049800100003 REFERENCE (J,JP/G,5,319,1979) 3049800100004 (C,77PUNE,2,240,1977) Abstract with graphs. 3049800100005 (P,BARC-990,75,1978) report, no data. 3049800100006 AUTHOR (B.Krishnarajulu,S.Sen,G.K.Mehta) 3049800100007 TITLE Light-charged-particle emission in keV neutron-induced 3049800100008 fission of Pu-239. 3049800100009 FACILITY (VDG,3INDITK) 2MV. 3049800100010 INC-SOURCE (P-LI7)Thickness of Li-target for 2MeV protons = 20keV.3049800100011 (P-T) Thickness of t-target for 2MeV protons = 100keV. 3049800100012 SAMPLE (94-PU-239,ENR=0.9697) 880 ug/cm2 Pu-239 foil, 3049800100013 purity=96.97%, active area=3 cm2. 3049800100014 METHOD (COINC).of fission fragments and LCP. 3049800100015 The natural alphas and fission fragments were stopped 3049800100016 in an Al foil before reaching the LCP-detector. 3049800100017 (PHD).on the fission side,cutoff energy = approx 6MeV, 3049800100018 on the LCP-side, cut-off energy = 8MeV. 3049800100019 Before and after each fast-neutron run, thermal runs 3049800100020 were performed to check the detector performance and 3049800100021 for normalization of the LCP-spectra. 3049800100022 DETECTOR (IOCH).Filled with high purity argon,pressure = 1atm. 3049800100023 (SIBAR).Surface-barrier,diameter=2cm,depletion depth= 3049800100024 400micro-m,mounted inside the ionization chamber, to 3049800100025 detect light charged particles ('LCP'). 3049800100026 A low intensity Ac-227 source was used for energy 3049800100027 calibration. 3049800100028 ANALYSIS A Gaussian was fitted by least squares method to the 3049800100029 measured spectra beyond 12MeV. The LCP-yields above 3049800100030 12MeV were attributed to alpha-particles alone. The 3049800100031 difference between measured spectra between 8 and 12MeV3049800100032 and Gaussian was assumed to be due to tritons. The 3049800100033 quoted alpha and triton yields -relative to thermal- 3049800100034 were obtained through this assumption. 3049800100035 CORRECTION The observed spectra were corrected for chance coinc. 3049800100036 Using singles LCP-spectra, then for energy losses in 3049800100037 the source, gas and Al foil. 3049800100038 ERR-ANALYS (DATA-ERR) No details given. 3049800100039 STATUS (TABLE) The numerical data were communicated 3049800100040 from G.K.Mehta.3049800100041 HISTORY (19790629C) TL. 3049800100042 (20090312A) SD:Updated to new date formats,lower case. 3049800100043 (20100303A) SD: REACTION code in Subent 002 was changed3049800100044 according to EXFOR rules. 3049800100045 (20211025U) VS. Reference BARC-990,75,1978 added. 3049800100046 MONITOR text moved to DETECTOR (SIBAR). 3049800100047 ENDBIB 45 0 3049800100048 NOCOMMON 0 0 3049800100049 ENDSUBENT 48 0 3049800199999 SUBENT 30498002 20100303 31443049800200001 BIB 5 8 3049800200002 REACTION (94-PU-239(N,F)2-HE-4,TER,KE) Maximum of fitted Gauss. 3049800200003 INC-SPECT Thermal neutrons were produced by placing a 3cm 3049800200004 paraffine block in the neutron path. 3049800200005 MONITOR (94-PU-239(N,F),TER,AKE,A,MXW) 3049800200006 MISC-COL (MISC1) Half width at half maximum of fitted Gaussian 3049800200007 (MISC2) Uncertainty of half-width. 3049800200008 HISTORY (20100303A) SD: REACTION code was changed 3049800200009 according to EXFOR rules. 3049800200010 ENDBIB 8 0 3049800200011 COMMON 3 3 3049800200012 MONIT MONIT-ERR EN-NRM 3049800200013 MEV MEV EV 3049800200014 1.6000E+01 1.0000E-01 2.5300E-02 3049800200015 ENDCOMMON 3 0 3049800200016 DATA 6 9 3049800200017 EN EN-RSL DATA DATA-ERR MISC1 MISC2 3049800200018 KEV KEV MEV MEV MEV MEV 3049800200019 2.5300E-05 1.6000E+01 1.0000E-01 4.6100E+00 1.3000E-013049800200020 1.4000E+02 3.0000E+01 1.5600E+01 9.0000E-02 4.5900E+00 1.3000E-013049800200021 1.7500E+02 3.0000E+01 1.6030E+01 1.0000E-01 4.2500E+00 1.4000E-013049800200022 2.0000E+02 3.0000E+01 1.5790E+01 1.8000E-01 5.0400E+00 1.6000E-013049800200023 2.6500E+02 3.0000E+01 1.6440E+01 1.0000E-01 4.4100E+00 1.4000E-013049800200024 3.0000E+02 3.0000E+01 1.5630E+01 1.0000E-01 4.7600E+00 1.4000E-013049800200025 5.7500E+02 1.0000E+02 1.5870E+01 1.2000E-01 5.3100E+00 1.6000E-013049800200026 7.9000E+02 1.1500E+02 1.5480E+01 1.1000E-01 4.9300E+00 1.5000E-013049800200027 9.9000E+02 1.3000E+02 1.5820E+01 1.4000E-01 4.7300E+00 1.9000E-013049800200028 ENDDATA 11 0 3049800200029 ENDSUBENT 28 0 3049800299999 ENDENTRY 2 0 3049899999999