4.3 Article

Sensitivity and Uncertainty Analysis of the GFR MOX Fuel Subassembly

期刊

NUCLEAR DATA SHEETS
卷 118, 期 -, 页码 545-547

出版社

ACADEMIC PRESS INC ELSEVIER SCIENCE
DOI: 10.1016/j.nds.2014.04.130

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资金

  1. Slovak Grant Agency for Science [1/0796/13]
  2. ERDF within the Research & Development Operational Program [ITMS 26240220073: 2.C.1.32]

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We performed sensitivity and uncertainty analysis as well as benchmark similarity assessment of the MOX fuel subassembly designed for the Gas-Cooled Fast Reactor (GFR) as a representative material of the core. Material composition was defined for each assembly ring separately allowing us to decompose the sensitivities not only for isotopes and reactions but also for spatial regions. This approach was confirmed by direct perturbation calculations for chosen materials and isotopes. Similarity assessment identified only ten partly comparable benchmark experiments that can be utilized in the field of GFR development. Based on the determined uncertainties, we also identified main contributors to the calculation bias.

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