ICONE19-43541 Conceptual Design Study for the Demonstration Reactor of JSFR : (4) Structural Design of Reactor Vessel

DOI Web Site

抄録

The concept of a compact reactor vessel has been formulated for the Japan Sodium-cooled Fast Reactor. In this concept, the reactor vessel is designed as a hot vessel to reduce the reactor vessel diameter. It is important to ensure structural integrity under both seismic and elevated-temperature conditions from the viewpoint of the structural designs for the hot reactor vessel. In this study, seismic evaluations were carried out, based on a seismic loading condition which had been revised after the Niigata-ken Chuetsu-oki Earthquake, occurred in Japan in 2007. Also, the thicknesses of the reactor vessel walls of a 750MWe-output plant and a 500MWe-output plant were determined from the viewpoint of buckling integrity, which resulted in 50mm for both plants. Buckling margins were evaluated to be more than 2.4. The difference in the plant outputs was negligible from the viewpoint of seismic design. Thermal integrity was evaluated under the condition that the reactor vessel wall is 50mm thick. Thermal ratcheting and creep-fatigue damage were evaluated under the three plant-start-up conditions of 2.2, 3.2, and 4.3 days. Thermal stress had to be lowered to avoid thermal ratcheting. As a result, the plant-start-up period needed more than 3.2 days for both plants. Thermal stress caused in both plants were nearly the same, and therefore the difference in the plant outputs was negligible from the viewpoint of thermal design. Hot vessel concept is acceptable for both plants under the conditions that the wall thickness is 50mm and the plant start-up period is 3.2 days.

収録刊行物

キーワード

詳細情報 詳細情報について

問題の指摘

ページトップへ