This article offers a summary of many interesting experiences and problems the authors have come across while making attempts to develop RAMBHA, the Kalpakkam processing code system for multigrouping neutron interaction cross section data for fast reactor applications. Many of the problems are due to limitations arising from the nature of computer facility including memory restraints. Also offered here is an interesting comparison of non-adjusted ENDF/B-IV based RRC multigroup cross-section set with 1969 adjusted French set. An attempt is made to highlight the impact of processing uncertainties on reactor parameters by two examples.
All Science Journal Classification (ASJC) codes
- Energy Engineering and Power Technology
- Nuclear Energy and Engineering