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Title: Development of a detailed core flow analysis code for prismatic fuel reactors

The development of a computer code for the analysis of the detailed flow of helium in prismatic fuel reactors is reported. The code, called BYPASS, solves, a finite difference control volume formulation of the compressible, steady state fluid flow in highly cross-connected flow paths typical of the Modular High-Temperature Gas Cooled Reactor (MHTGR). The discretization of the flow in a core region typically considers the main coolant flow paths, the bypass gap flow paths, and the crossflow connections between them. 16 refs., 5 figs.
Authors:
Publication Date:
OSTI Identifier:
6645795
Report Number(s):
EGG-M-90249; CONF-901101--7
ON: DE90013092; TRN: 91-010567
DOE Contract Number:
AC07-76ID01570
Resource Type:
Conference
Resource Relation:
Conference: American Nuclear Society winter meeting, Washington, DC (USA), 11-15 Nov 1990
Research Org:
EG and G Idaho, Inc., Idaho Falls, ID (USA)
Sponsoring Org:
DOE/NE
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; HELIUM; FLUID FLOW; HTGR TYPE REACTORS; REACTOR COOLING SYSTEMS; B CODES; COMPUTER CODES; FLOW MODELS; FLUID MECHANICS; FUEL ASSEMBLIES; REACTOR CHANNELS; REACTOR CORES; COOLING SYSTEMS; ELEMENTS; ENERGY SYSTEMS; FLUIDS; GAS COOLED REACTORS; GASES; GRAPHITE MODERATED REACTORS; MATHEMATICAL MODELS; MECHANICS; NONMETALS; RARE GASES; REACTOR COMPONENTS; REACTORS 210300* -- Power Reactors, Nonbreeding, Graphite Moderated