文档介绍：Available online at
Nuclear Engineering and Design 238 (2008) 287–298
Main R&D issues for fast reactor structural design standard
Naoto Kasahara a,∗, Kyotada Nakamura a, Masaki Morishita a,
Hiroshi Shibamoto b, Kazuhiko Inoue b
a Advanced Nuclear System Research and Development Directorate, Japan Atomic Energy Agency,
4002 Narita, Oarai, Higashi Ibaraki, Ibaraki 311-1393, Japan
b The Japan Atomic pany, Japan
Accepted 4 August 2006
Abstract
For realization of economical and reliable fast reactor (FR) plants, the Japan Atomic Energy Agency (JAEA) and the Japan Atomic -
pany (JAPC) are cooperating on the “Feasibility Study mercialized 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 mercialized 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 ponents where thermal loads are dominant.
© 2006 Elsevier . All rights reserved.
1. Introduction 2. Structural design characteristics of sodium
components of fast reactors
The Japan Atomic Energy Agency (JAEA) and the Japan
Atomic pany (JAPC) are cooperating to conduct a FRs adopt liquid metal as a coolant for effective heat removal
research and development program called the “Feasibility Study from core without neutron moderation. Liqu