ENTRY 30658 20090830 31403065800000001 SUBENT 30658001 20090830 31403065800100001 BIB 16 36 3065800100002 TITLE (n,2n) cross-section measurement of Nb-93, Au-197 and 3065800100003 U-238 with fission-neutron spectrum 3065800100004 AUTHOR (G.Shani) 3065800100005 INSTITUTE (3ISLNEG) 3065800100006 EXP-YEAR (1982) 3065800100007 REFERENCE (J,ANE,10,(9),473,1983) 3065800100008 SAMPLE Half-inch diameter foils of Nb-0.13847 g, Au-1.2215 g, 3065800100009 depleted U(0.3% U-235)-0.24388 g, Al-0.03669 g 3065800100010 MONITOR ((MONIT1)41-NB-93(N,INL)41-NB-93-M,,SIG) 3065800100011 ((MONIT2)13-AL-27(N,A)11-NA-24,,SIG) 3065800100012 MONIT-REF ((MONIT1),G.SHANI,J,NT,51,83,1980) for Nb-93 3065800100013 ((MONIT2),A.CALAMAND,R,IAEA-156,1974) for Al-27 3065800100014 INC-SOURCE (CF252) 300 Micro-g Cf-252 neutron source 3065800100015 METHOD (ACTIV) Samples were irradiated for 7 days.Measurements3065800100016 were repeated six times for each sample. 3065800100017 DETECTOR (GELI) Ge(Li) detector 45cc, 1.9keV resolution at 3065800100018 1.17 MeV 3065800100019 (NAICR) Several measurements were made for a comparison3065800100020 with a calibrated 3x3 inch Na-I scintillator 3065800100021 (SCIN) Neutron spectrum was measured with a 0.5x0.5inch3065800100022 NE213 liquid scintillator. 3065800100023 PART-DET (DG) 3065800100024 ERR-ANALYS (ERR-T) Errors given include the following: 3065800100025 * Self-absorption in the foil 3065800100026 * Detector efficiency 3065800100027 (ERR-S,,1.) Statistical error (less than 1%) 3065800100028 * Spread of value for each measurement 3065800100029 INC-SPECT Fission spectrum from a Cf-252 source 3065800100030 STATUS (TABLE) Data taken from 3065800100031 Ann.Nucl.Energy,10,no9,(1983),473, Table 1. 3065800100032 HISTORY (19831011C) DG.- 3065800100033 (19840507U) DG.-Cosmetic changes in Bib and Common 3065800100034 sections.- 3065800100035 (19930316A) HW.-San 002-004: 'FIS' added in SF8 of 3065800100036 reaction code.- 3065800100037 (20090725A) SD:Updated to new date formats,lower case. 3065800100038 ENDBIB 36 0 3065800100039 COMMON 3 3 3065800100040 EN-DUMMY MONIT1 MONIT2 3065800100041 MEV B MB 3065800100042 2. 1.88 0.725 3065800100043 ENDCOMMON 3 0 3065800100044 ENDSUBENT 43 0 3065800199999 SUBENT 30658002 20090830 31403065800200001 BIB 3 3 3065800200002 REACTION (41-NB-93(N,2N)41-NB-92-M,,SIG,,FIS) 3065800200003 DECAY-DATA (41-NB-92-M,10.15D,DG,394.,0.99) 3065800200004 HISTORY (19930316A) HW.- 'FIS' added in SF8 of reaction code.- 3065800200005 ENDBIB 3 0 3065800200006 NOCOMMON 0 0 3065800200007 DATA 2 1 3065800200008 DATA ERR-T 3065800200009 MB MB 3065800200010 0.549 0.070 3065800200011 ENDDATA 3 0 3065800200012 ENDSUBENT 11 0 3065800299999 SUBENT 30658003 20090830 31403065800300001 BIB 3 3 3065800300002 REACTION (79-AU-197(N,2N)79-AU-196,,SIG,,FIS) 3065800300003 DECAY-DATA (79-AU-196,6.18D,DG,356.,0.94) 3065800300004 HISTORY (19930316A) HW.- 'FIS' added in SF8 of reaction code.- 3065800300005 ENDBIB 3 0 3065800300006 NOCOMMON 0 0 3065800300007 DATA 2 1 3065800300008 DATA ERR-T 3065800300009 MB MB 3065800300010 4.3 0.5 3065800300011 ENDDATA 3 0 3065800300012 ENDSUBENT 11 0 3065800399999 SUBENT 30658004 20090830 31403065800400001 BIB 3 3 3065800400002 REACTION (92-U-238(N,2N)92-U-237,,SIG,,FIS) 3065800400003 DECAY-DATA (92-U-237,6.7D,DG,208.,0.23) 3065800400004 HISTORY (19930316A) HW.- 'FIS' added in SF8 of reaction code.- 3065800400005 ENDBIB 3 0 3065800400006 NOCOMMON 0 0 3065800400007 DATA 2 1 3065800400008 DATA ERR-T 3065800400009 MB MB 3065800400010 12.2 1.5 3065800400011 ENDDATA 3 0 3065800400012 ENDSUBENT 11 0 3065800499999 ENDENTRY 4 0 3065899999999