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

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6645795

Bennett, R G

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.

• Research Organization: EG and G Idaho, Inc., Idaho Falls, ID (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6645795
• Report Number(s): EGG-M-90249; CONF-901101-7; ON: DE90013092; TRN: 91-010567
• Resource Relation: Conference: American Nuclear Society winter meeting, Washington, DC (USA), 11-15 Nov 1990
• Country of Publication: United States
• Language: English

Related Subjects

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