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Title: Experimental Modeling of VHTR Plenum Flows during Normal Operation and Pressurized Conduction Cooldown

Abstract

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.

Authors:
;
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
DOE - NE
OSTI Identifier:
911716
Report Number(s):
INL/EXT-06-11760
TRN: US0800101
DOE Contract Number:  
DE-AC07-99ID-13727
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 - GENERAL STUDIES OF NUCLEAR REACTORS; BENCHMARKS; ELECTRICITY; HYDROGEN; NATURAL CONVECTION; NUCLEAR POWER; PRODUCTION; SAFETY; SIMULATION; WORKING FLUIDS; mixing; natural circulation; NGNP; plenum flow; thermal stratification; VHTR

Citation Formats

McCreery, Glenn E, and Condie, Keith G. Experimental Modeling of VHTR Plenum Flows during Normal Operation and Pressurized Conduction Cooldown. United States: N. p., 2006. Web. doi:10.2172/911716.
McCreery, Glenn E, & Condie, Keith G. Experimental Modeling of VHTR Plenum Flows during Normal Operation and Pressurized Conduction Cooldown. United States. https://doi.org/10.2172/911716
McCreery, Glenn E, and Condie, Keith G. 2006. "Experimental Modeling of VHTR Plenum Flows during Normal Operation and Pressurized Conduction Cooldown". United States. https://doi.org/10.2172/911716. https://www.osti.gov/servlets/purl/911716.
@article{osti_911716,
title = {Experimental Modeling of VHTR Plenum Flows during Normal Operation and Pressurized Conduction Cooldown},
author = {McCreery, Glenn E and Condie, Keith G},
abstractNote = {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.},
doi = {10.2172/911716},
url = {https://www.osti.gov/biblio/911716}, journal = {},
number = ,
volume = ,
place = {United States},
year = {Fri Sep 01 00:00:00 EDT 2006},
month = {Fri Sep 01 00:00:00 EDT 2006}
}