Integrity assessment considering unified constraint for reactor pressure vessel under pressurized thermal shock-Reference-Cited by-同舟云学术

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Integrity assessment considering unified constraint for reactor pressure vessel under pressurized thermal shock

Published:2023-09 Issue: Volume:290 Page:109508
ISSN:0013-7944
Container-title:Engineering Fracture Mechanics
language:en
Short-container-title:Engineering Fracture Mechanics

Author:

Zheng Y.,Wang G.Z.,Tu S.T.,Xuan F.Z.

Funder

National Natural Science Foundation of China

Publisher

Elsevier BV

Subject

Mechanical Engineering,Mechanics of Materials,General Materials Science

Reference46 articles.

1. Fracture studies on reactor pressure vessel subjected to pressurised thermal shock: a review;Thamaraiselvi;Nucl Eng Des,2020

2. Rules for Construction of Nuclear Facility Components;ASME Bpvc Section III,2007

3. Rules for Inservice Inspection of Nuclear Power Plant Components;ASME Bpvc Section XI,2007

4. International Atomic Energy Agency, Guidelines for application of the Master Curve approach to reactor pressure vessel integrity in nuclear power plants, Austria, 2005, IAEA.

5. The master curve method: a new concept for brittle fracture;Wallin;Int J Mater Product Tech,1999

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1. Development of pressure-temperature limit curves considering unified constraint for reactor pressure vessel;International Journal of Pressure Vessels and Piping;2024-02

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