Abstract.Sampling based method is adopted in many fields of engineering and it is currently used to propagate uncertainties from physical parameters and from nuclear data, to integral indicators of nuclear systems. The total uncertainty associated with a model simulation is of major importance for safety analysis and to guide vendors about acceptable tolerance limits for nuclear installations parts. This work presents some calculations to propagate uncertainties for a nuclear reactor fuel element modeled in SCALE/TRITON, using the sampling tool SCALE/SAMPLER. Results showed that the influence of input uncertainties on k inf is more pronounced in the fresh core other than the depleted core and the contribution from studied manufacturing uncertainties is smaller than the contribution of nuclear data uncertainties.
Thorium can be utilized in Pressurized Water Reactors (PWR) as ThO2 fuel matrix supported by fissile materials. In this analysis, VVER-1000 reactor was taken as a representative of the PWR reactor group. The thorium fuel matrix was mixed with fissile material in form of pure 233 U, enriched uranium (19.7 % enrichment) and Reactor-Grade plutonium. Whole fuel cycles were analysed by ANDREA nodal code with diffusion data prepared by HELIOS calculations. Equilibrium fuel loadings were achieved for all fuel composition for four different lengths of fuel loadings reaching from 4×12 months to 5×18 months. The process of reaching the equilibrium loadings, fissile material requirements, and fundamental operational parameters are presented.
scite is a Brooklyn-based organization that helps researchers better discover and understand research articles through Smart Citations–citations that display the context of the citation and describe whether the article provides supporting or contrasting evidence. scite is used by students and researchers from around the world and is funded in part by the National Science Foundation and the National Institute on Drug Abuse of the National Institutes of Health.