Trends in Reactor Pressure Vessel and Circuit DevelopmentR. W. Nichols |
Contents
Some Remarks Related to the Requirements for Development | 15 |
Utilisation of Indian Point Unit 1 for Research to Support | 27 |
Problems Involved in the Specification of the Chemical | 33 |
Copyright | |
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alloy analysis ASME austenite Axial bainite brittle capsules casting CEGB chemical cladding Code components composition corrosion crack arrest temperature CRD housing defect detection design improvements diameter ductile effect embrittlement examination fabrication failure fatigue crack growth ferritic flaws fracture mechanics fracture toughness grain boundary heat treatment heat-affected zone IAEA ingot inservice inspection inside integral irradiation Japan light water reactor load machining manufacturing material mechanical properties method microstructure mock-up neutron nondestructive nondestructive testing notch nozzle nuclear power operation parameters performed plant plate pressure boundary pressure vessel steels Pressurised problems procedures programme reactor pressure vessel reactor vessel recrystallised reduce region reliability requirements ring safety Section segregation shell shown in Fig Škoda SRCS stress intensity stress relief cracks structure surface surveillance techniques temper embrittlement tensile thickness tube ultrasonic upper shelf variation weld seams weldments yield strength