Published January 1980
| Version v1
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COBRA-WC model and predictions for a fast-reactor natural-circulation transient
Description
The COBRA-WC (Whole Core) code has been used to predict the core-wide coolant and rod temperature distribution in a liquid metal fast reactor during the early part (first 220 seconds) of a natural circulation transient. Approximately one-sixth of the core was modeled including bypass flows and the pressure losses above and below the core region. Detailed temperature and flow distributions were obtained for the two test fuel assemblies. The COBRA-WC model, the approach, and predictions of core-wide transient coolant and rod temperatures during a natural circulation transient are presented in this paper
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A03/MF A01 as DE82008556.
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Additional details
Additional titles
- Augmented title (English)
- LMFBR
Publishing Information
- Imprint Pagination
- 30 p.
- Report number
- PNL-SA--8318
Conference
- Title
- 19. national heat transfer conference.
- Dates
- 27 - 30 Jul 1980.
- Place
- Orlando, FL, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13699440
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- HEAT TRANSFER; HYDRAULICS; LMFBR TYPE REACTORS; LOSS OF FLOW; MATHEMATICAL MODELS; NATURAL CONVECTION; REACTOR CORES; REACTOR SAFETY; SPATIAL DISTRIBUTION
- Descriptors DEC
- ACCIDENTS; BREEDER REACTORS; CONVECTION; DISTRIBUTION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SAFETY
Optional Information
- Secondary number(s)
- CONF-800723--30.