Title of article
Structural integrity assessment of aging nuclear reactor pressure vessels Original Research Article
Author/Authors
W.E. Pennell، نويسنده , , S.N.M. Malik، نويسنده ,
Issue Information
روزنامه با شماره پیاپی سال 1997
Pages
21
From page
27
To page
47
Abstract
Irradiation embrittlement reduces both the cleavage fracture toughness and the ductile tearing toughness of reactor pressure vessel (RPV) steels. Extensive research programs have investigated the fracture behavior of heavy-section vessels containing flaws. Information obtained from that research has been used to develop regulatory guidance for evaluating the structural integrity of irradiated RPVs. Additional research programs have developed fracture analysis methods, and generated the data required for their implementation. Regulatory guidance employs fracture analysis technology to assure that adequate fracture-prevention margins for RPVs are maintained throughout the licensed operating period of nuclear power plants.
Journal title
Nuclear Engineering and Design Eslah
Serial Year
1997
Journal title
Nuclear Engineering and Design Eslah
Record number
888255
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