MELCOR validation results
Description
Recent comparisons of MELCOR predictions to three sets of experiments, the ABCOVE Aerosol Experiments, the HDR-V44 Steam Blowdown Experiments, and the Battelle-Frankfurt Gas Mixing Experiments are presentd. All three comparisons involve conditions that are of concern in an LWR containment during a severe accident. MELCOR results are compared to the experimental data and the predictions of at least one other state-of-the-art code for each test. In the ABCOVE comparisons, the MELCOR aerosol modeling is demonstrated. In comparisons to the HDR-V44 Steam Blowdown Experiments, MELCOR predictions of the response of the containment to the release of steam from the primary system are shown, and in the Battelle-Frankfurt comparisons, MELCOR predictions of the diffusion in a containment of an injected hydrogen-nitrogen gas are studied. These comparisons provide critical testing of the MELCOR control volume hydrodynamics package, the radionuclide package, and the flow path package
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 - GPO as TI87002495.
Files
Additional details
Publishing Information
- Imprint Pagination
- 18 p.
- Report number
- SAND--86-2128C
Conference
- Title
- 14. water reactor safety information meeting.
- Dates
- 27-31 Oct 1986.
- Place
- Gaithersburg, MD (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18052503
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BLOWDOWN; BWR TYPE REACTORS; COMPUTERIZED SIMULATION; CONTAINMENT; FISSION PRODUCTS; HEAT TRANSFER; HYDRAULICS; M CODES; PWR TYPE REACTORS; RADIOACTIVE AEROSOLS; REACTOR ACCIDENTS; VERIFICATION
- Descriptors DEC
- ACCIDENTS; AEROSOLS; COLLOIDS; COMPUTER CODES; DISPERSIONS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; ISOTOPES; MATERIALS; POWER REACTORS; RADIOACTIVE MATERIALS; REACTORS; SIMULATION; SOLS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-8610135--8.