Fracture evaluation of surface cracks in light water reactor pressure vessels under pressurized thermal shock loading-Reference-Cited by-同舟云学术

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Fracture evaluation of surface cracks in light water reactor pressure vessels under pressurized thermal shock loading

Published:1990-05 Issue:2 Volume:8 Page:121-136
ISSN:0261-9180
Container-title:High Temperature Technology
language:en
Short-container-title:High Temperature Technology

Author:

Kussmaul K.,Sauter A.,Stegmeyer R.,Guth W.

Publisher

Informa UK Limited

Subject

General Engineering

Link

http://www.tandfonline.com/doi/pdf/10.1080/02619180.1990.11753467

Reference1 articles.

1. Kussmaul, K., Blind, D. and Jansky, J.‘Safety analysis of circumferentially cracked feed water piping of light water reactors’. In7th SMiRT, Post-Conference Seminar on Assuring Structural Integrity of Steel Reactor Pressure Boundary Components, Chicago(August 1983)

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. Fatigue crack growth calculations for a vessel internal corner crack under repeated thermal transients;International Journal of Pressure Vessels and Piping;1997-05

2. Investigations concerning the crack resistance behaviour of thick-walled components under thermal shock loading;Steel Research;1990-04

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