Critical crack depth diagram of reactor vessel for pressurized thermal shock

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

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