Материал портала ядерных знаний BelNET
статья/документ по запросу ресурса "6047"
doi:10.1016/j.anucene.2024.110806 2024-12-12 Annals of Nuclear Energy Volume 212, March 2025, 110806 There is a rise in sensitivity and uncertainty analyses with respect to nuclear data, which are a basis for a neutron transport simulation. The analyses are primarily concerned with the state-of-the-art reactors, known as Generation IV. They provide assessments of nuclear data performance, key nuclear data, and their uncertainty influence on functionals such as the eigenvalue, reactivity coefficients, delayed neutron fraction, etc. In this work, recent advances in sensitivity and uncertainty analysis with corresponding transport codes are reviewed. Furthermore, the available results of the analyses are compared and discussed. As a result, this review summarizes current analyses performed for the advanced systems in recent years. The gaps in the Generation IV system analyses are noted including SCWRs, MSFRs of different types, and other systems. Besides, the gaps in nuclear data of state-of-the-art libraries are discussed. Based upon this, these gaps can become a part of analyses for identifying future nuclear data needs. |
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