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Journal Articles

Core and safety design for France-Japan common concept on sodium-cooled fast reactor

Takano, Kazuya; Oki, Shigeo; Ozawa, Takayuki; Yamano, Hidemasa; Kubo, Shigenobu; Ogura, Masashi*; Yamada, Yumi*; Koyama, Kazuya*; Kurita, Koichi*; Costes, L.*; et al.

EPJ Nuclear Sciences & Technologies (Internet), 8, p.35_1 - 35_9, 2022/12

The France and Japan teams have carried out collaborative works to have common technical views regarding a sodium-cooled fast reactor concept. Japan has studied the feasibility of an enhanced high burnup low-void effect (CFV) core and fuel using oxide dispersion-strengthened steel cladding in ASTRID 600. Regarding passive shutdown capabilities, Japan team has performed a preliminary numerical analysis for ASTRID 600 using a complementary safety device, called a self-actuated shutdown system (SASS), one of the safety approaches of Japan. The mitigation measures of ASTRID 600 against a severe accident, such as a core catcher, molten corium discharge assembly, and the sodium void reactivity features of the CFV core, are promising to achieve in-vessel retention for both countries. The common design concept based on ASTRID 600 is feasible to demonstrate the SFR core and safety technologies for both countries.

Journal Articles

OECD/NEA expert group on uncertainty analysis for criticality safety assessment; Current activities

Ivanova, T.*; Fernex, F.*; Kolbe, E.*; Vasiliev, A.*; Lee, G. S.*; Woo, S. W.*; Mennerdahl, D.*; Nagaya, Yasunobu; Neuber, J. C.*; Hoefer, A.*; et al.

Proceedings of International Conference on Physics of Reactors; Advances in Reactor Physics to Power the Nuclear Renaissance (PHYSOR 2010) (CD-ROM), 15 Pages, 2010/05

The expert group (EG) on Uncertainty Analysis for Criticality Safety Assessment (UACSA) was established within the OECD/NEA Working Party on Nuclear Criticality Safety in December 2007 to promote exchange of information on related topics; compare methods and software tools for uncertainty analysis; test their performance; and assist in selection/development of safe and efficient methodologies for validation of criticality computations. At the current stage, the work of the group is focused on approaches for validation of criticality calculations. With the diversity of the approaches to validate criticality calculations, a thorough description of each approach and assessment of its performance is useful to the criticality safety community. Developers, existing and potential practitioners as well as reviewers of assessments using those approaches should benefit from this effort. Exercise Phase I was conducted in order to illustrate predicting capabilities of criticality validation approaches, which include similarity assessment, definition of $$k_mathit{eff}$$ bias and bias uncertainty, and selection of benchmarks. The approaches and results of the exercises will be thoroughly documented in a pending state-of-the-art report from the EG. This paper provides an overview of current and future activities for the EG, a summary of the participant-contributed validation approaches, and a synthesis of the results for the exercises.

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