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Title: Computational Flow Predictions for the Lower Plenum of a High-Temperature, Gas-Cooled Reactor

Advanced gas-cooled reactors offer the potential advantage of higher efficiency and enhanced safety over present day nuclear reactors. Accurate simulation models of these Generation IV reactors are necessary for design and licensing. One design under consideration by the Very High Temperature Reactor (VHTR) program is a modular, prismatic gas-cooled reactor. In this reactor, the lower plenum region may experience locally high temperatures that can adversely impact the plant’s structural integrity. Since existing system analysis codes cannot capture the complex flow effects occurring in the lower plenum, computational fluid dynamics (CFD) codes are being employed to model these flows [1]. The goal of the present study is to validate the CFD calculations using experimental data.
Authors:
Publication Date:
OSTI Identifier:
911905
Report Number(s):
INL/CON-06-11334
TRN: US0800204
DOE Contract Number:
DE-AC07-99ID-13727
Resource Type:
Conference
Resource Relation:
Conference: ANS 2006 Winter Meeting,Albuquerque, NM,11/12/2006,11/16/2006
Research Org:
Idaho National Laboratory (INL)
Sponsoring Org:
DOE - NE
Country of Publication:
United States
Language:
English
Subject:
22 - GENERAL STUDIES OF NUCLEAR REACTORS; COMPUTERIZED SIMULATION; DESIGN; EFFICIENCY; FLUID MECHANICS; GAS COOLED REACTORS; LICENSING; REACTORS; SAFETY; SIMULATION prismatic reactor, gas-cooled reactor