Structural integrity of water reactor pressure boundary components. Progress report ending 2 February 1977

Technical Report · Sun May 01 04:00:00 EDT 1977

OSTI ID:7219133

Loss, F J ^[1]

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1. ed.

Research progress is presented for a continuing program to characterize materials properties performance with respect to structural integrity of light water reactor pressure boundary components. Progress for this reporting period is summarized in the following areas: (a) radiation embrittlement resistance of A533-B Class 1 steel plate as a function of extra low copper impurity content; (b) influence of phosphorus and copper content on post-irradiation upper shelf toughness and postirradiation toughness recovery for A533-B steel plate and weld metal; (c) investigations of warm prestress and plastic net ligament phenomena as a means to mitigate crack extension in a vessel during a loss of coolant accident; and (d) evaluation of critical factors in crack growth rate studies in pressurized water reactor environment.

• Research Organization: Naval Research Lab., Washington, DC (USA)
• OSTI ID: 7219133
• Report Number(s): NRL/NUREG-3512
• Country of Publication: United States
• Language: English

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