Research Program Plan: Reactor vessels
Milton Vagins, U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Engineering Technology
Division of Engineering Technology, Office of Nuclear Regulatory Research,, U.S. Nuclear Regulatory Commission, 1985 - Nuclear pressure vessels
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analysis annealing of reactor Appendix G application assisted fatigue crack ASTM behavior benchmarks calculations Charpy chemical elements cladding compact tensile complete conducted constitutive equations copper content crack arrest data data base documents dosimetry ductile elements environmentally assisted fatigue EPRI evaluation fatigue crack growth flaw fluence flux fracture mechanics fracture toughness HSST Irradiation Series HSST program initiation irradiated material laboratories LEFM loading MEBR metallurgical methodology micromechanism model n/cm neutron nuclear reactor Nuclear Regulatory Commission Nuclear Regulatory Research Office of Nuclear ORNL parameters plans power reactor pressure vessel steels pressurized thermal shock procedures PWR environments radiation embrittlement reactor pressure vessels reactor vessel reembrittlement research program S-N Curves Section XI specific standards stress surveillance capsules thermal annealing toughness properties toughness values unified fracture unirradiated and irradiated University of Buffalo University of Maryland upper shelf energy vessel annealing vessel wall warm prestressing weld weldments Westinghouse