Published 1990
| Version v1
Report
Restricted
Development of a detailed core flow analysis code for prismatic fuel reactors
Description
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
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A03/MF A01 as DE90013092; OSTI; INIS; US Govt. Printing Office Dep.
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Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 15 p.
- Report number
- EGG-M--90249
Conference
- Title
- American Nuclear Society (ANS) winter meeting.
- Dates
- 11-15 Nov 1990.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 22069565
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- B CODES; COMPUTER CODES; FLOW MODELS; FLUID FLOW; FLUID MECHANICS; FUEL ASSEMBLIES; HELIUM; HTGR TYPE REACTORS; REACTOR CHANNELS; REACTOR COOLING SYSTEMS; REACTOR CORES
- Descriptors DEC
- COOLING SYSTEMS; ELEMENTS; GAS COOLED REACTORS; GRAPHITE MODERATED REACTORS; MATHEMATICAL MODELS; MECHANICS; NONMETALS; RARE GASES; REACTOR COMPONENTS; REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Secondary number(s)
- CONF-901101--7.