Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors

Author:

Yoon Ji-Hyun,Lee Bong-Sang

Funder

National Research Foundation of Korea

MSIP

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference9 articles.

1. Integrity of Reactor Pressure Vessels in Nuclear Power Plants: Assessment of Irradiation Embrittlement Effects in Reactor Pressure Vessel Steels;IAEA,2009

2. Reactor Pressure Vessel Status Report, NUREG-1511, Supp.2, US NRC;Carpenter,2000

3. Regulatory Guide 1.99, Revision 2, Radiation Embrittlement of Reactor Vessel Materials;US NRC,1988

4. New methodologies for developing radiation embrittlement models and trend developing radiation embrittlement models and trend curves of the Charpy impact test data;Wang,2003

5. A physically-based correlation of irradiation-induced transition temperature shifts for RPV Steels;Eason;J. Nucl. Mater.,2013

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