15-P - 31 FUJI E.C. EVAL-MAY87 H.NAKAMURA DIST-DEC21 20090828 ----JENDL-5 MATERIAL 1525 -----INCIDENT NEUTRON DATA ------ENDF-6 FORMAT History 21-11 revised by O.Iwamoto (MF8/MT4,16,22,28,102,103,107) added 21-11 above 20 MeV, JENDL-4.0/HE merged by O.Iwamoto 21-11 (MF6/MT5) recoil spectrum added by O.Iwamoto =========================================================== The data were taken from JENDL-3.3. =========================================================== HISTORY 87-05 Newly evaluated by H.Nakamura (fuji electric co.ltd) 93-12 JENDL-3.2 Total cross section was recalculated by T.Watanabe. (khi) Gamma-ray production cross sections were evaluated by T. Asami (de). ***** modified parts for JENDL-3.2 ****************************** (3,1) A new omp set was determined. (3,2) total - nonelastic (3,107) Q-value corrected mf=12,13,14,15 newly evaluated ****************************************************************** 01-07 (3,103) revised. Compiled by K.Shibata (jaeri) for JENDL-3.3 ****** modified parts for JENDL-3.3 ********************* (1,451) Updated. (3,1) Re-calculated. (3,2) Re-calculated. (3,103) Taken from JENDL Dosimetry File 99 (3,251) Deleted. (4,2) Transformation matrix deleted. (5,16-91) INT=22 *********************************************************** mf=1 General information mt=451 Descriptive data and dictionary mf=2 mt=151 Resonance parameters: Resolved resonances for MLBW formula : 1.0e-5 eV - 500 keV Parameters are taken from BNL 325 4th edition/1/, and Macklin et al./2/. Cross sections calculated with these parameters were corrected by adding mf=3, mt=1,2 and 102 data. calculated 2200-m/s cross sections and resonance integrals 2200-m/sec res. integ. ref. elastic 3.134 b - /1/ capture 0.166 b 0.081 b /1/ total 3.300 b - mf=3 Neutron cross sections Below 500 keV background cross section. mt=1,2 0.07029 b Above 500 keV mt=1 New optical model calculation using the parameter set determined by T. Watanabe V = 50.58 - 0.06476E (MeV) Ws = 6.583 + 0.5927E (MeV) Vso= 3.391 (MeV) r = 1.36, a = 0.422(fm) rs= 1.23, b = 0.517(fm) rso=0.938, aso=0.600(fm) mt=2 total - nonelastic mt=4,51-56,91,102 Total, elastic, inelastic and capture Calculated with casthy code/3/, considering the competition with the threshold reaction channels. Optical potential parameters of Fu/4/ are adjusted to reproduce the following experimental data: mt=1 total NESTORr data (many authors) mt=2 elastic - mt=4 inelastic - The spherical optical potential parameters: V=43.0 Vso=5.37 (MeV) Ws=9.13 Wv =0.0 (MeV) r =rso=1.26 rs=1.39 (fm) a=aso=0.76 b=0.40 (fm) mt=102 Capture data are normalized to 1.8 mb at 500 keV based on (7 mb at 30 keV) by Macklin et al./5/. The discrete level scheme taken from ref./6/: no. energy (MeV) spin-parity (g.s.) 0.0 1/2 - 1 1.266 3/2 + 2 2.234 5/2 + 3 3.134 1/2 + 4 3.295 5/2 + 5 3.415 7/2 + 6 3.506 3/2 + Continuum levels assumed above 4.0 MeV. The level density parameters of Asano et al. /7/ are used. mt=16 (n,2n), 22(n,n'a), 28(n,n'p), 103(n,p), 107(n,a) Based on the statistical model calculations with gnash code /8/, without the precompound reaction correction. Transmission coefficients for proton and alpha particle are calculated by using the omp of Becchetti-Greenlees /9/ and Huizenga-Igo/10/, respectively. In the cases of mt=103 and 107, the experimental data were also considered together with the calculations. Level density parameters are based on built-in values. ***** For JENDL-3.3 ************************************* The (n,p) reaction cross section was taken from JENDL Dosimetry File 99 (JENDL/D-99). The evaluation is based on the experimental data /12-24/ and nuclear model calculation by Strohmaier/25/. *********************************************************** mf=4 Angular distributions of secondary neutrons mt=2 Calculated with optical model(casthy). mt=51-56 Calculated with hauser-feshbach formula(casthy) mt=16,22,28 Isotropic in the laboratory system. mt=91 Isotropic distributions in cm were converted to the distributions in lab. mf=5 Energy distributions of secondary neutrons mt=16,22,28,91 Evaporation spectra. mf=12 Photon production multiplicity mt=102,103,107 Calculated by sincros-ii/11/. mf=13 Photon production cross section mt=3 Calculated by sincros-ii/11/. mt=4 Discrete lines calculated by taking account of branching ratios mf=14 Photon angular distribution mt=3,4,102,103,107 Isotropic mf=15 Photon energy distribution mt=3,103,107 Calculated by sincros-ii/11/. mt=102 Calculated by casthy/3/. 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