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Verification of nuclear calculation methodology and preliminary uncertainty quantification in a sodium-cooled fast reactor

Ikeda, Kazumi*; Homma, Yuto*; Moriwaki, Hiroyuki*; Oki, Shigeo 

This paper treats the verification of nuclear calculation methodology of control rod reactivity and the uncertainty quantification of calculation model in order to design a next demonstration fast breeder reactor, Japan Sodium cooled Fast Reactor. Verification and validation of design methodology is required and various kinds of uncertainty in nuclear characteristics should be comprehensively assessed. This study starts in pursuit of them in the context of preliminary conceptual design. First, this work compares the calculation results of the deterministic calculation method with Monte Carlo one in order to verify it. Second, the uncertainties associated with the calculation model are preliminarily estimated based on the correction values. Consequently, it is naturally concluded that the nuclear calculation methodology can precisely prospect that of control rod reactivity, representing the mathematical model with the specified limit of accuracy.



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