High Temperature Postirradiation Materials Performance of Spent Pressurized Water Reactor Fuel Rods under Dry Storage Conditions
Autor: | Sharon D. Atkin, David E. Stellrecht, V. Pasupathi, Robert E. Einziger |
---|---|
Rok vydání: | 1982 |
Předmět: |
Nuclear and High Energy Physics
Materials science Waste management 020209 energy Zirconium alloy Pressurized water reactor 02 engineering and technology Condensed Matter Physics Fuel element failure Rod law.invention 020303 mechanical engineering & transports 0203 mechanical engineering Nuclear Energy and Engineering Creep law 0202 electrical engineering electronic engineering information engineering Comminution Post Irradiation Examination Inert gas Nuclear chemistry |
Zdroj: | Nuclear Technology. 57:65-80 |
ISSN: | 1943-7471 0029-5450 |
Popis: | Postirradiation studies on failure mechanisms of well-characterized pressurized water reactor rods were conducted for up to a year at 482, 510, and 571°C in limited air and inert gas atmospheres. N... |
Databáze: | OpenAIRE |
Externí odkaz: |