Trends in Reactor Pressure Vessel and Circuit DevelopmentR. W. Nichols |
Contents
Current Technical Technical Aspects Concerning PWR Vessel | 7 |
Some Remarks Related to the Requirements for Development | 15 |
Utilisation of Indian Point Unit 1 for Research to Support | 27 |
Copyright | |
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alloy analysis ASME Code austenite bainite brittle capsules carbide casting CEGB cladding components cooling corrosion crack arrest temperature crack growth rates defect ductile effects examination fabrication factor failure fatigue crack growth ferritic flange flaws forging fracture mechanics fracture toughness grain boundary grain boundary segregation heat treatment heat-affected zone hydrogen ingot inservice inspection integral irradiation Japan light water reactor load manufacturing material mechanical properties metallurgical method microstructure mock-up neutron nondestructive nondestructive testing notch nozzle nuclear power operation parameters pipe plant plate pressure boundary pressure vessel steels Pressurised problems procedures programme quenching reactor pressure vessel reactor vessel recrystallised reduce reliability requirements safety Section shell shown in Fig Škoda specimens steam steelmaking stress corrosion cracking stress intensity stress relief cracks structure surface surveillance temper embrittlement tensile thickness transients transition temperature tube ultrasonic variation weld seams yield strength