Summary report on new regulatory codes and criteria and guidelines: IAEA guidelines for WWER reactor coolant system integrity assessment-Reference-Cited by-同舟云学术

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Summary report on new regulatory codes and criteria and guidelines: IAEA guidelines for WWER reactor coolant system integrity assessment

Published:2000-03 Issue:1 Volume:196 Page:93-100
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Havel Radim

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

Reference20 articles.

1. US Code of Federal Regulations, Energy,1991

2. Ranking of Safety Issues of WWER-440/230 NPPs,1992

3. Reactor Pressure Vessel Embrittlement,1992

4. WWER-440 Model 230 Reactor Pressure Vessel Embrittlement and Annealing,1992

5. Applicability of the Leak Before Break Concept,1993

Cited by 3 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. CFD simulation on the transient process of coolant mixing phenomenon in reactor pressure vessel;Annals of Nuclear Energy;2021-04

2. Evaluation of tube to collector connection by hydraulic expansion method in PGV-1000 steam generators;Nuclear Engineering and Design;2011-02

3. Failure analysis of collector body in WWER-1000 nuclear power plants;Engineering Failure Analysis;2010-09

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