Search
CSV
RISDevelopment of Leak Before Break Assessment Method for Japan Sodium Cooled Fast Reactor Pipe—Part 1 Crack Opening Displacement Assessment of Thin Wall Pipes Made of Modified 9Cr 1Mo Steel
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This was carried out to establish crack opening displacement (COD) evaluation methods used in leakbeforebreak (LBB) assessment of sodium pipes of the Japan sodium cooled fast reactor (JSFR). For sodium pipes of JSFR, the ...
Comparison and Assessment of the Creep Fatigue Evaluation Methods With Notched Specimen Made of Mod.9Cr 1Mo Steel
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: In components design at elevated temperature, creepfatigue is one of the most important failure modes, and assessment of creepfatigue life in structural discontinuities is an important issue in evaluating the integrity of ...
ARKADIA—For the Innovation of Advanced Nuclear Reactor Design
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: This paper describes the outline and development plan for “Advanced Reactor Knowledge- and Artificial Intelligence (AI)-aided design integration approach through the whole plant lifecycle (ARKADIA),” which the Japan Atomic ...