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Main R&D issues for fast reactor structural design standard
Authors:Naoto Kasahara   Kyotada Nakamura   Masaki Morishita   Hiroshi Shibamoto  Kazuhiko Inoue
Affiliation:aAdvanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency, 4002 Narita, Oarai, Higashi Ibaraki, Ibaraki 311-1393, Japan;bThe Japan Atomic Power Company, Japan
Abstract:For realization of economical and reliable fast reactor (FR) plants, the Japan Atomic Energy Agency (JAEA) and the Japan Atomic Power Company (JAPC) are cooperating on the “Feasibility Study on Commercialized FR Cycle Systems”. To certify the design concepts through evaluation of the structural integrity of FR plants, the research and development of the “Elevated Temperature Structural Design Guide for Commercialized Fast Reactor (FDS)” is recognized as an essential theme. The FDS focuses on particular failure modes of FRs such as ratchet deformation and creep-fatigue damage due to cyclic thermal loads. For precise evaluation of these modes, the research and development for three main issues is in progress. First, the “Refinement of Failure Criteria” needs to be addressed for particular failure modes of FRs. Secondly, the development of “Guidelines for Inelastic Design Analysis” is conducted to predict elastic plastic and creep deformation under elevated temperature conditions. Lastly, efforts are being made toward preparing “Guidelines for Thermal Load Modeling” for the design of FR components where thermal loads are dominant.
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