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

[21] Development of flow-induced vibration evaluation methodology for large-diameter piping with elbow in Japan sodium-cooled fast reactor
Advanced Nuclear System R and D Directorate, Japan Atomic Energy Agency, 4002 Narita, O-arai, Ibaraki 311-1393, Japan
不详
Nucl Eng Des, 11 (4464-4475):
[22] Research and development of high-rise steel structural BIM software and its application in Shanghai Center Project
Ji, Jun
Zhang, Qilin
Yang, Huizhu
Chang, Zhiguo
Dongnan Daxue Xuebao (Ziran Kexue Ban)/Journal of Southeast University (Natural Science Edition), 2009, 39 (SUPPL. 2): : 205 - 211
[23] Research and development of measurement method for structural fracturing process in shake table tests using image processing technique
Dept. of Mech. Eng., Tokyo Denki University, 2-2, Kanda-Nisiki-cho, Chiyoda-ku, Tokyo 101-8457, Japan
不详
不详
1600, 115-121 (February 2004):
[24] Research on APP development and design for personalized bio-health management from the perspective of digital health
Shunmei, Lin
Journal of Commercial Biotechnology, 2022, 27 (04) : 60 - 66
[25] Evaluation procedure for sodium environmental effects on 316FR and modified 9Cr-1Mo steel for the structural design of Japanese fast breeder reactors
Oarai Engineering Center, Japan Nucl. Cycle Devmt. Institute, Ibaraki, Japan
ASME Pressure Vessels Piping Div Publ PVP, 1600, (61-66):
[26] Development of LBB assessment method for Japan sodium cooled fast reactor (JSFR) PIPES (5) crack growth assessment method for pipes made of MOD.9CR-1MO steel
Wakai, Takashi
Machida, Hideo
Yoshida, Shinji
Tokiyoshi, Takumi
Kikuchi, Koichi
Xu, Yang
Tsukimori, Kazuyuki
American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, 2011, 6 (PARTS A AND B): : 715 - 722

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