Trends in Reactor Pressure Vessel and Circuit DevelopmentR. W. Nichols |
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Page 147
... parameters recorded . 4.1 . Principle of the Method The principle is to follow the evolution of the best physical parameters characterising the loading conditions with respect to the stresses involved , and to combine the transients ...
... parameters recorded . 4.1 . Principle of the Method The principle is to follow the evolution of the best physical parameters characterising the loading conditions with respect to the stresses involved , and to combine the transients ...
Page 149
... parameters for each transient are taken separately if the time interval between the transients is longer than T ( see Fig . 4 ( a ) for determination of T ) , the stress being then back to the initial state ; or the physical parameters ...
... parameters for each transient are taken separately if the time interval between the transients is longer than T ( see Fig . 4 ( a ) for determination of T ) , the stress being then back to the initial state ; or the physical parameters ...
Page 278
... parameters of a flaw into an isometric , two - dimensional image with the aid of specialised computer logic . The coordinates of the isomeric view can then be continuously varied , thus providing the analyst a dynamic , three ...
... parameters of a flaw into an isometric , two - dimensional image with the aid of specialised computer logic . The coordinates of the isomeric view can then be continuously varied , thus providing the analyst a dynamic , three ...
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