Construction codes developed for prototype FBR Monju-Reference-Cited by-同舟云学术

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Construction codes developed for prototype FBR Monju

Published:1987-01 Issue:3 Volume:98 Page:283-288
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Iida Kunihiro,Asada Yasuhide,Okabayashi Kunio,Nagata Takashi

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Cited by 26 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Key technologies for future sodium-cooled fast reactors;Sodium-cooled Fast Reactors;2022

2. Ratcheting in pressurized pipes and equipment: A review on affecting parameters, modelling, safety codes, and challenges;Fatigue & Fracture of Engineering Materials & Structures;2018-02-14

3. Creep–fatigue evaluation method for weld joints of Mod.9Cr–1Mo steel. Part I: Proposal of the evaluation method based on finite element analysis and uniaxial testing;Nuclear Engineering and Design;2017-11

4. Corrosion phenomena induced by liquid metals in Generation IV reactors;Structural Materials for Generation IV Nuclear Reactors;2017

5. Creep-fatigue evaluation method for weld joint of Mod.9Cr-1Mo steel Part II: Plate bending test and proposal of a simplified evaluation method;Nuclear Engineering and Design;2016-12

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