Trends in Reactor Pressure Vessel and Circuit DevelopmentR. W. Nichols |
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Page 112
R. W. Nichols. Kic K1 AK a Q β α NOMENCLATURE critical stress intensity factor calculated stress intensity factor range of stress intensity factors acting stress crack size crack shape factor function of free surface da / d N crack ...
R. W. Nichols. Kic K1 AK a Q β α NOMENCLATURE critical stress intensity factor calculated stress intensity factor range of stress intensity factors acting stress crack size crack shape factor function of free surface da / d N crack ...
Page 117
... stress intensity factor based on the single crack size is increased , particularly on the inner , that is on that side of the crack front which is turned towards another crack . The experimental results of Holdulak and Kleins are shown ...
... stress intensity factor based on the single crack size is increased , particularly on the inner , that is on that side of the crack front which is turned towards another crack . The experimental results of Holdulak and Kleins are shown ...
Page 142
... stress intensity which are applied to a certain number of critical points , use of the fatigue curves of the material and knowledge of the Young's modulus evolution as a function of temperature makes it possible to determine the ...
... stress intensity which are applied to a certain number of critical points , use of the fatigue curves of the material and knowledge of the Young's modulus evolution as a function of temperature makes it possible to determine the ...
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