Critical crack depth diagram of reactor vessel for pressurized thermal shock-Reference-Cited by-同舟云学术

Critical crack depth diagram of reactor vessel for pressurized thermal shock

Published:2009-03 Issue:3 Volume:239 Page:425-433
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Jhung Myung Jo,Choi Young Hwan

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

Reference12 articles.

1. ASME, 2004, Rules for inservice inspection of nuclear power plant components, ASME Boiler and Pressure Vessel Code, Section XI, American Society of Mechanical Engineers.

2. Documentation of Probabilistic Fracture Mechanics Codes used for Reactor Pressure Vessels Subjected to Pressurized Thermal Shock Loading, EPRI TR-105001;Balky,1995

3. A model for predicting the influence of warm pre-stressing and strain aging on the cleavage fracture toughness of ferritic steels;Curry;International Journal of Fracture,1983

4. Probabilistic structural integrity of a PWR pressure vessel–PROSIR round robin;Faidy,2007

5. The effect of postulated flaw on structural integrity of RPV dusing PTS;Jhung;Nuclear Engineering and Technology,2007

Cited by 5 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. Elastic and elastoplastic fracture analysis of a reactor pressure vessel under pressurized thermal shock loading;European Journal of Mechanics - A/Solids;2017-11

2. Ultimate bearing capacity analysis of a reactor pressure vessel subjected to pressurized thermal shock with XFEM;Engineering Failure Analysis;2017-10

3. Nonlinear numerical study of crack initiation and propagation in a reactor pressure vessel under pressurized thermal shock using XFEM;Fatigue & Fracture of Engineering Materials & Structures;2017-08-10

4. Ultimate Bearing Capacity Analysis and Sizing Optimization of a Cracked Reactor Pressure Vessel in the Coupled Thermo-Mechanical Field;Journal of Failure Analysis and Prevention;2017-06-26

5. The deterministic structural integrity assessment of reactor pressure vessels under pressurized thermal shock loading;Nuclear Engineering and Design;2015-07