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 |