JENDL-4.0/HE incident proton library 0 0 7.015000+3 1.487130+1 -1 0 6 1 728 1451 1 0.000000+0 0.000000+0 0 0 0 6 728 1451 2 9.986200-1 2.000000+8 0 0 10010 4 728 1451 3 0.000000+0 0.000000+0 0 0 93 6 728 1451 4 7-N - 15 EVAL-APR14 T.MURATA, K.Kosako 728 1451 5 DIST-Nov20 REV- 728 1451 6 ----JENDL-4.0/HE MATERIAL 728 REVISION 0 728 1451 7 -----INCIDENT PROTON DATA 728 1451 8 ------ENDF-6 FORMAT 728 1451 9 728 1451 10 ****************************************************** 728 1451 11 728 1451 12 --- JENDL-4.0/HE --- 728 1451 13 728 1451 14 High-energy Evaluation up to 200 MeV 728 1451 15 728 1451 16 ****************************************************** 728 1451 17 728 1451 18 HISTORY 728 1451 19 2014-04 New evaluation was made by T.Murata (JENDL Committee). 728 1451 20 2014-10 Compilation was made by K.Kosako (Shimizu). 728 1451 21 728 1451 22 MF=1 General Information 728 1451 23 MT=451 Description data and dictionary 728 1451 24 728 1451 25 MF=3 Cross sections 728 1451 26 These quantities evaluated or calculated in two or three 728 1451 27 energy regions described below and are interpolated between 728 1451 28 two regions of about energies rather arbitrarily. 728 1451 29 728 1451 30 MT=2 (Elastic - Rutherford) cross section 728 1451 31 MT=3 Non elastic cross section 728 1451 32 Below Ep=7.0 MeV, the experimental elastic angular distri- 728 1451 33 butions /1/ were analyzed with resonance formula and the 728 1451 34 resonance energies and widths are obtained. Then, the 728 1451 35 elastic scattering cross sections were calculated and the 728 1451 36 evaluation of mt=2 and mt=3 are made. 728 1451 37 Above Ep=7.0 MeV, calculated cross sections with TOTELA-3 728 1451 38 /2/ are adopted. 728 1451 39 MT=102 Radiative capture cross section 728 1451 40 Below Ep=15 MeV, evaluation were made on the experimental 728 1451 41 cross sections /3/. 728 1451 42 Above Ep=15 MeV: TENDL-2009 /4/ cross sections are adopted 728 1451 43 and extrapolated up to Ep>=200 MeV. 728 1451 44 MT=5 Total particle production cross section 728 1451 45 Neutron: Below Ep=12 MeV, evaluation were made on the 728 1451 46 experimental cross sections /5/. In the energy region 728 1451 47 12 MeV