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Report No.

Study on Advanced Structural Design for Commercialized Fast Breeder Reactors

Morishita, Masaki ; Aoto, Kazumi ; Kasahara, Naoto; Asayama, Tai ; Inoue, Kazuhiko*; Shibamoto, Hiroshi*; Tanaka, Yoshihiko*

Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Power Company(JAPC) launched joint research programs on structural design and three-dimensional seismic isolation technologies, as part of the supporting R&D activities for the feasibility studies on commerdalized fast breeder reactor cycle systems. A research project by JAPC under the auspices of the Ministry of Economy, Trade, and Industry (METI) with technical support by JNC is included in this joint study, This report contains the results of the research on the structural design technology. The research scope was identified as (1) FDS(FBR Design Standard), (2) Standardization of new material, and (3)System Based Code for Integrity, and the results of this year's studies are summarized as follows. (1)FDS (FBR Design Standard) * As for failure criteria, ratcheting-fatigue tests were continued. Applicability of rational settling method on creep design regime was evaluated and evaluation method of primary stress was studied. * As for a guideline on inelastic analysis for design, development of conservative detail modle (CRIEPI model for design) is underway. Loading history effect was evaluated through analysis. Conservative evaluation method of creep-fatigue damage coped with inelastic analysis was also developed. Aiming for verification of the guidline, structure model test simulated sodium surface level of reactor vessel is continuing. Policy and items of the guideline were studied. * As for a guideline on thermal loads modeling for design, provisions of the guideline on rational settling method of thermal striping loads were discussed. Screening method to grasp severe thermal load and parts in higher stress was developed. (2)Standardization of new material * As for candidate 12-chromium stainless steel (added tungsten, non-added tungsten), that is expected to improve strength of components of commercialized fast reactor, short and medium-term strength tests (including long-term aged test piece), ob



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