Trends in Reactor Pressure Vessel and Circuit DevelopmentR. W. Nichols |
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Page 1
... reactor pressure components demands a consequent analysis of the decisive parameters such as materials , design ... light water reactor technology , extensive material investigations on actual components were carried out . Because ...
... reactor pressure components demands a consequent analysis of the decisive parameters such as materials , design ... light water reactor technology , extensive material investigations on actual components were carried out . Because ...
Page 13
... Reactor Pressure Vessel used in Light Water Power Plants by Advanced Material Fabrication and Testing Technologies ' , Fourth International Conference on Structural Mechanics in Reactor Technology , 15-19 Aug. 1977 , San Francisco ...
... Reactor Pressure Vessel used in Light Water Power Plants by Advanced Material Fabrication and Testing Technologies ' , Fourth International Conference on Structural Mechanics in Reactor Technology , 15-19 Aug. 1977 , San Francisco ...
Page 81
... reactor pressure vessels . This is also one of the main tasks of research and development work in the field of light water reactor investigations in the Czechoslovak Socialist ... Light Water Reactors against Brittle Fractures BRUMOVSKY.
... reactor pressure vessels . This is also one of the main tasks of research and development work in the field of light water reactor investigations in the Czechoslovak Socialist ... Light Water Reactors against Brittle Fractures BRUMOVSKY.
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