Development and validation of multi-group cross-section library for subcritical energy reactor

As the fusion-driven subcritical energy reactor has wide and complex energy spectrum, multigroup cross-section library needs to be developed for its design requirement. A 187-group neutron cross-section library is developed by using NJOY code. With transport code ANISN, enriched uranium critical sphere benchmarks and uranium sphere model with water cavity are calculated to validate the multigroup cross-section library Multi-layer shell model of subcritical energy reactor is calculated, and the results are compared with MCNP5. The results show that the multigroup cross-section library is correct and can be used for subcritical energy reactor design, and the reaction rates and neutron spectra in subcritical energy reactor can be calculated as well. (authors)