Structural Integrity of Water Reactor Pressure Boundary Components.

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