CODE NUCLIDE ORIGINAL DATA TAKEN FROM MODIFICATION ADDITIONAL FILE MODIFICATIONS ORIGINAL DATA TAKEN FROM MODIFICATION ADDITIONAL FILE MODIFICATIONS ORIGINAL DATA TAKEN FROM MODIFICATION ADDITIONAL FILE MODIFICATIONS NUCLIDE COMMENTS
1020046 20-Ca- 46 JEFF-3.1.1 / JEFF-3.1 Updated The total, total elastic and total nonelastic cross sections were zero in the JEFF-3.1 file in the 1.e-5 - 1.e3 eV energy range. This has been fixed by assuming MT2 = 2.9 barn, MT3=MT102 and MT1 = MT2 + MT102. JEFF-3.1 / New evaluation / NRG-2004: n + Ca-46