Development of a detailed core flow analysis code for prismatic fuel reactors
The detailed analysis of the core flow distribution in prismatic fuel reactors is of interest for modular high-temperature gas-cooled reactor (MHTGR) design and safety analyses. Such analyses involve the steady-state flow of helium through highly cross-connected flow paths in and around the prismatic fuel elements. Several computer codes have been developed for this purpose. However, since they are proprietary codes, they are not generally available for independent MHTGR design confirmation. The previously developed codes do not consider the exchange or diversion of flow between individual bypass gaps with much detail. Such a capability could be important in the analysis of potential fuel block motion, such as occurred in the Fort St. Vrain reactor, or for the analysis of the conditions around a flow blockage or misloaded fuel block. This work develops a computer code with fairly general-purpose capabilities for modeling the flow in regions of prismatic fuel cores. 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 MHTGR.
- OSTI ID:
- 5603184
- Report Number(s):
- CONF-901101-; CODEN: TANSA
- Journal Information:
- Transactions of the American Nuclear Society; (USA), Vol. 62; Conference: American Nuclear Society (ANS) winter meeting, Washington, DC (USA), 11-15 Nov 1990; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR CORES
REACTOR SAFETY
B CODES
GAS FLOW
HEAT TRANSFER
PRISMATIC CONFIGURATION
ACCURACY
COMPUTER CODES
COMPUTERIZED SIMULATION
CONTROL ELEMENTS
CONVERGENCE
FLOW BLOCKAGE
FUEL ELEMENTS
HELIUM
ITERATIVE METHODS
JACOBIAN FUNCTION
MODULAR STRUCTURES
NEUTRON ABSORBERS
NONLINEAR PROBLEMS
PERFORMANCE
STEADY-STATE CONDITIONS
VALIDATION
VERIFICATION
CONFIGURATION
ELEMENTS
ENERGY TRANSFER
FLUID FLOW
FLUIDS
FUNCTIONS
GAS COOLED REACTORS
GASES
GRAPHITE MODERATED REACTORS
NONMETALS
RARE GASES
REACTOR COMPONENTS
REACTORS
SAFETY
SIMULATION
TESTING
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
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