Development And Preliminary Analysis Of The Burn-up Nuclear Data Library For Fast Reactor

Evaluated nuclear data file released by each country contains complete nuclear data, it is convenient to storage、 retrieval communication. However, it cannot directly used for numerical simulation calculation, such as transport calculation and burnup calculation in nuclear reactor design and research. Consequently, many data processing codes and data libraries were developed to meet the need of scientific research and engineering design by nuclear application research institutes.A fast reactor library for ORIGEN-S based on ENDF/B-VII.0was developed in this paper. The format of the new library conforms to the light water reactor data library format included in ORIGEN-S. which consists of three parts of data, decay data, fission-product yields and cross-section data. Decay data was stored in a single file while fission-product yields data and cross-section data were stored in another file. Decay data processed by FBDEC and fission-product yields that contains fission yield data for30fissionable actinides processed by FBFP. The pointwise cross-sections were collapsed to a three-group structure using a fast reactor neutron flux spectrum in the cross-section library by NJOY99.Preliminary validations were performed with fast reactor benchmark published by OECD/NEA using the new library. Isotopic composition variation during cycles was compared with results calculated by other laboratories. Further validation should be performed in the future. Updated library ensured precise calculation results that improve the economic benefit of each section in nuclear industry.