2023 Annual Meeting

Presentation information

Planning Lecture

Over view Report » Research Committee for Mechanistic Evaluation of Critical Heat Flux for Nuclear Reactors[Co-organized by Thermal-Hydraulics Division, Computational Science and Engineering Division]

[2J_PL] Activity report of research committee for mechanistic evaluation of critical heat flux for nuclear reactors

Tue. Mar 14, 2023 1:00 PM - 2:30 PM Room J (13 Bildg.2F 1321)

Chair:Tomio Okawa(UEC)

[2J_PL01] Current status of experimental studies and measurement techniques in pool boiling

*Shinichiro Uesawa1 (1. JAEA)

An evaluation method of critical heat flux based on a mechanism is needed to design the fuel assemblies in light water reactors efficiently and evaluate safety appropriately. The research committee for mechanistic evaluation of critical heat flux for nuclear reactors reviewed many studies and organized issues to be considered to establish the evaluation method of critical heat flux based on the mechanism. In this session, the activities and discussion results of the research committee will be reported.