A review of the ASME low upper shelf toughness evaluation procedures for nuclear reactor pressure vessels-Reference-Cited by-同舟云学术

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A review of the ASME low upper shelf toughness evaluation procedures for nuclear reactor pressure vessels

Published:1991-10 Issue:3 Volume:130 Page:259-266
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Griesbach T.J,Smith E

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

Reference10 articles.

1. Code of Federal Regulations Title 10, Part 50, Appendix G, Fracture toughness requirements,1988

2. Resolution of the Task A-11 Reactor Vessel Materials Toughness Safety Issue;Johnson;U.S. Nuclear Regulatory Commission Report NUREG 0744,1982

3. Classification and characterization of materials by means of fracture mechanics parameters

4. Size Effects on J—R curves for A 302-B Plate;Hiser,1989

5. Evaluation of upper shelf toughness requirements for reactor pressure vessels;Gamble,1989

Cited by 2 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. Applications of Elastic-Plastic Fracture Mechanics in Section XI, ASME Code Evaluations;Online Companion Guide to the ASME Boiler and Pressure Vessel Codes;2020-01-01

2. Effects of steady ductile crack growth on cleavage fracture from three-dimensional, small-scale yielding simulations;Engineering Fracture Mechanics;2014-09

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