Technical support for the EPRI [Electric Power Research Institute] debris coolability requirement for advanced light water reactors
Description
The Electric Power Research Institute (EPRI) advanced light water reactor (ALWR) design requirement for cavity sizing to promote long-term core debris coolability specifies that the reactor containment be arranged to afford a floor area for potential core debris spreading of at least 0.02 square meters per thermal megawatt of reactor power. This requirement has substantial experimental and analytical support as a sufficient basis to ensure long-term debris coolability. A logical framework and presentation of such support is provided in this document. The evidence as presented demonstrates that, following vessel failure, core debris in the cavity would consist of a mixture of fragments and a relatively continuous, but porous and cracked, phase that would be distributed relatively uniformly over the area that would be available per the requirement. Considering pertinent operative heat transfer phenomena, it is also demonstrated that the heat removal rate from core debris in this configuration would be sufficient to ensure debris coolability in the reactor cavity, even when the cavity is flooded after vessel failure. 29 refs., 6 figs., 8 tabs
Availability note (English)
MF available from INIS under the Report Number; NTIS, PC A04/MF A01 as DE90013095; OSTI; INIS; US Govt. Printing Office Dep.
Files
Additional details
Additional titles
- Subtitle (English)
- Advanced Reactor Severe Accident Program
Publishing Information
- Imprint Pagination
- 74 p.
- Report number
- DOE/ID--10278
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21076048
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Descriptors DEI
- BWR TYPE REACTORS; CAVITIES; CONCRETES; CONTAINMENT; COOLING; CORIUM; D CODES; FLOW RATE; HEAT FLUX; HEAT TRANSFER; HYDRAULICS; MATHEMATICAL MODELS; MELTDOWN; PWR TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MATERIALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC07-76ID01570
- Secondary number(s)
- MISC--90057.