The present paper was presented at the JEFF (OECD/NEA Data Bank) Working Group Meeting on Benchmark Testing, Data Processing and Evaluations in September 1998. It describes the features of a pointwise neutron cross section library below 20 MeV, processed in the ACE format for the MCNP Monte Carlo transport code with the NJOY-94.66 nuclear data processing system. This library was produced in the Nuclear Data Centre of ENEA-Bologna for nuclear fission applications. The library is based on the ENDF/B-VI Release 3 evaluated data files and contains 86 materials (natural elements and isotopes including fission products) processed up to eight temperatures: 300 °K, 500 °K, 560 °K, 760 °K, 800 °K, 1000 °K, 1500 °K and 2200 °K. The processed data include gamma-production data when the basic ENDF/B-VI evaluated data files contain these data. The present library has been satisfactorily tested in thermal and fast criticality benchmarks. For analyses below 20 MeV, this library can be applied also in cell and core calculations dedicated to the study of the subcritical accelerator driven systems (ADS).
|Titolo:||MCB6.BOLIB - An ENDF/B-VI Library for the MCNP Monte Carlo Code|
|Data di pubblicazione:||17-set-1998|
|Appare nelle tipologie:||4.1 Contributo in Atti di convegno|