Experimental Modeling of VHTR Plenum Flows During Normal Operation and Pressurized Conduction Cooldown.

McCreery, G. E. ; Condie, K. G.

Technical Information Center Oak Ridge Tennessee

关键词: VHTR reactor;    Flow models;    Plenum flows;    Modeling;    Very high temperature reactor(VHTR);   

RP-ID  :  DE2007911716

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

The Very High Temperature Reactor (VHTR) is the leading candidate for the Next Generation Nuclear Power (NGNP) Project in the U.S. which has the goal of demonstrating the production of emissions free electricity and hydrogen by 2015. The present document addresses experimental modeling of flow and thermal mixing phenomena of importance during normal or reduced power operation and during a loss of forced reactor cooling (pressurized conduction cooldown) scenario. The objectives of the experiments are, (1), provide benchmark data for assessment and improvement of codes proposed for NGNP designs and safety studies, and, (2), obtain a better understanding of related phenomena, behavior and needs. Physical models of VHTR vessel upper and lower plenums which use various working fluids to scale phenomena of interest are described. The models may be used to both simulate natural convection conditions during pressurized conduction cooldown and turbulent lower plenum flow during normal or reduced power operation.