Published January 1985
| Version v1
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Decay heat removal and dynamic plant testing at EBR-II
Description
The complete testing program at EBR-II directed towards transient thermal-hydraulic performance is described. The program, which was initially directed towards an understanding of the dynamics of natural convective flow and the validation of related computer codes, has evolved into studies of unprotected transients. These later tests are intended to provide experimental data as well as to directly demonstrate the inherently safe response of an LMR to transients which in the recent past were thought to lead to core disruption. Tpical results and conclusions from the series of protected natural circulation tests are also presented
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A03/MF A01; 1 as DE85006211.Files
16064896.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 26 p.
- Report number
- CONF-850420--3
Conference
- Title
- 2. specialists' meeting on decay heat removal and natural convection in LMFBRs.
- Dates
- 17-19 Apr 1985.
- Place
- Long Island, NY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 16064896
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; COMPUTER CODES; EBR-2 REACTOR; HEAT TRANSFER; HYDRAULICS; PIPES; REACTOR COOLING SYSTEMS; REACTOR CORES; REACTOR SAFETY; TESTING; THERMAL ANALYSIS
- Descriptors DEC
- BREEDER REACTORS; COOLING SYSTEMS; ENERGY TRANSFER; EPITHERMAL REACTORS; EXPERIMENTAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SODIUM COOLED REACTORS