Thermal and stress analyses of the reactor pressure vessel lower head of the three mile island unit 2-Reference-Cited by-同舟云学术

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Thermal and stress analyses of the reactor pressure vessel lower head of the three mile island unit 2

Published:1992-01 Issue:1 Volume:52 Page:25-40
ISSN:0308-0161
Container-title:International Journal of Pressure Vessels and Piping
language:en
Short-container-title:International Journal of Pressure Vessels and Piping

Author:

Hashimoto K.,Onizawa K.,Kurihara R.,Kawasaki S.,Soda K.

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference6 articles.

1. A scenario of the Three Mile Island Unit 2 accident;Broughton;Nucl. Technol.,1989

2. TMI-2 Vessel Investigation Project (VIP) metallurgical program;Diercks,1990

3. Estimated TMI-2 vessel thermal response bounds based on the lower plenum debris configuration;Moore,1988

4. Comparison of thermal and mechanical responses of the Three Mile Island Unit 2 reactor vessel;Thinnes;Nucl. Technol.,1989

Cited by 4 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. Analysis of thermal-force coupling stress field under the temperature of alternating of molecular sieve adsorption tower;E3S Web of Conferences;2021

2. Global rupture of a nuclear reactor lower head with elevated temperature due to severe accidents;Nuclear Engineering and Design;1999-03

3. Thermomechanical analysis with finite and boundary element methods — A bibliography (1992–1994);Finite Elements in Analysis and Design;1995-05

4. Local creep rupture failure modes on a corium-loaded lower head;Nuclear Engineering and Design;1994-07

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