JENDL-5.0 N-15 0 0 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 5 728 1451 3 0.000000+0 0.000000+0 0 0 115 6 728 1451 4 7-N - 15 EVAL-APR14 T.MURATA, K.Kosako 728 1451 5 DIST-Dec21 REV- 728 1451 6 ----JENDL-5.0 MATERIAL 728 REVISION 0 728 1451 7 -----INCIDENT PROTON DATA 728 1451 8 ------ENDF-6 FORMAT 728 1451 9 728 1451 10 History 728 1451 11 2021-12 Data were taken from the previous library/1/ where the 728 1451 12 recoil spectra were added to MF6/MT5/ZAP if exist. 728 1451 13 (O.Iwamoto and S.Kunieda) 728 1451 14 728 1451 15 ****************************************************** 728 1451 16 * * 728 1451 17 * --- JENDL-5.0 --- * 728 1451 18 * * 728 1451 19 * Incident proton data up to 200 MeV * 728 1451 20 * * 728 1451 21 ****************************************************** 728 1451 22 728 1451 23 References 728 1451 24 1) S.Kunieda+, JAEA-Conf 2016-004, 41 (2016). 728 1451 25 728 1451 26 728 1451 27 ################################################## 728 1451 28 ### Descriptive texts of previous data ### 728 1451 29 ################################################## 728 1451 30 728 1451 31 728 1451 32 ****************************************************** 728 1451 33 728 1451 34 --- JENDL-4.0/HE --- 728 1451 35 728 1451 36 High-energy Evaluation up to 200 MeV 728 1451 37 728 1451 38 ****************************************************** 728 1451 39 728 1451 40 HISTORY 728 1451 41 2014-04 New evaluation was made by T.Murata (JENDL Committee). 728 1451 42 2014-10 Compilation was made by K.Kosako (Shimizu). 728 1451 43 728 1451 44 MF=1 General Information 728 1451 45 MT=451 Description data and dictionary 728 1451 46 728 1451 47 MF=3 Cross sections 728 1451 48 These quantities evaluated or calculated in two or three 728 1451 49 energy regions described below and are interpolated between 728 1451 50 two regions of about energies rather arbitrarily. 728 1451 51 728 1451 52 MT=2 (Elastic - Rutherford) cross section 728 1451 53 MT=3 Non elastic cross section 728 1451 54 Below Ep=7.0 MeV, the experimental elastic angular distri- 728 1451 55 butions /1/ were analyzed with resonance formula and the 728 1451 56 resonance energies and widths are obtained. Then, the 728 1451 57 elastic scattering cross sections were calculated and the 728 1451 58 evaluation of mt=2 and mt=3 are made. 728 1451 59 Above Ep=7.0 MeV, calculated cross sections with TOTELA-3 728 1451 60 /2/ are adopted. 728 1451 61 MT=102 Radiative capture cross section 728 1451 62 Below Ep=15 MeV, evaluation were made on the experimental 728 1451 63 cross sections /3/. 728 1451 64 Above Ep=15 MeV: TENDL-2009 /4/ cross sections are adopted 728 1451 65 and extrapolated up to Ep>=200 MeV. 728 1451 66 MT=5 Total particle production cross section 728 1451 67 Neutron: Below Ep=12 MeV, evaluation were made on the 728 1451 68 experimental cross sections /5/. In the energy region 728 1451 69 12 MeV