Research and development issues for Fast Reactor Structural Design Standard (FDS)

被引：0

作者：

Kasahara, Naoto ^{[1
]}

Ando, Masanori ^{[1
]}

Morishita, Masaki ^{[1
]}

Shibamoto, Hiroshi ^{[2
]}

Tanaka, Yoshihiko ^{[2
]}

Inoue, Kazuhiko ^{[2
]}

机构：

[1] Japan Nucl. Cycle Devmt. Institute, 4002 Narita, Oarai, Ibaraki, 311-13, Japan

[2] Japan Atomic Power Company, 4002 Narita, Oarai, Ibaraki, 311-13, Japan

来源：

ASME Pressure Vessels Piping Div Publ PVP | 1600年 / 25-32期

关键词：

Compendex;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

Accident prevention - Data reduction - Engineering research - Failure analysis - Fast reactors - High temperature effects - Mathematical models - Standards

引用

共 26 条

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[8] BASIC NUCLEAR DATA AND THE FAST REACTOR SHIELDING DESIGN FORMULAIRE PROPANE Do.
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