Trends in Reactor Pressure Vessel and Circuit DevelopmentR. W. Nichols |
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Page 13
... Pressure Vessel Nozzles and Corresponding Stress Analysis ' , Third International Conference on Pressure Vessel Technology , Tokyo ( 1977 ) , Part I , pp . 263-74 . 4. K. KUSSMAUL , et al . , ' Enhancement of the Quality of the Reactor ...
... Pressure Vessel Nozzles and Corresponding Stress Analysis ' , Third International Conference on Pressure Vessel Technology , Tokyo ( 1977 ) , Part I , pp . 263-74 . 4. K. KUSSMAUL , et al . , ' Enhancement of the Quality of the Reactor ...
Page 82
... reactor and its active core . The injury or even the destruction of these ... vessel would result in a long - lasting shutdown of the reactor and thereby also in a ... pressure vessels are made against brittle failures must 82 M. BRUMOVSKY.
... reactor and its active core . The injury or even the destruction of these ... vessel would result in a long - lasting shutdown of the reactor and thereby also in a ... pressure vessels are made against brittle failures must 82 M. BRUMOVSKY.
Page 83
R. W. Nichols. which the pressure vessels are made against brittle failures ... reactor and the so - called ' hot cells ' , to evaluate the properties of ... vessel is free of any defects whatsoever . In reality , however , such a material ...
R. W. Nichols. which the pressure vessels are made against brittle failures ... reactor and the so - called ' hot cells ' , to evaluate the properties of ... vessel is free of any defects whatsoever . In reality , however , such a material ...
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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Common terms and phrases
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