Independent analysis of selected core-concrete interaction and fission product release experiments with CORCON-MOD2 and VANESA
Description
The discrepancies between experimental findings and the Reactor Safety Study predictions, as well as the rapidly developing data base enabling phenomenological modeling of core-concrete interactions and ex-vessel fission product release, have prompted the development of several new computer models of core-concrete interactions and fission product release during severe accidents. Two such models are the CORCON-MOD2 model of core-concrete interactions and the VANESA model of ex-vessel aerosol and fission product release during core-concrete interactions. The final judge on the adequacy of the development of models of core debris-concrete interactions is, of course, comparison of the model predictions with the results of experiments. The research into ex-vessel core debris behavior differs from research into many aspects of reactor accidents in that there are many experimental results for comparison. Comparisons of code predictions with results of tests using realistic temperatures and conditions should provide an indication of the progress that has been made and, with appropriately chosen tests, an indication of work that needs to be done. 9 refs., 6 figs., 5 tabs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01; 1 as TI86009430.Files
17078545.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 11 p.
- Report number
- BNL-NUREG--37869
Conference
- Title
- Thermal reactor safety meeting.
- Dates
- 2-6 Feb 1986.
- Place
- San Diego, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 17078545
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AEROSOLS; COMPARATIVE EVALUATIONS; CONCRETES; CONTAINMENT BUILDINGS; CORIUM; EVALUATION; FISSION PRODUCT RELEASE; FLUID-STRUCTURE INTERACTIONS; HEAT FLUX; MATHEMATICAL MODELS; REACTOR ACCIDENTS; REACTOR SAFETY; STEEL-CR19NI10; URANIUM DIOXIDE; ZIRCONIUM OXIDES
- Descriptors DEC
- ACCIDENTS; ACTINIDE COMPOUNDS; ALLOYS; AUSTENITIC STEELS; BUILDING MATERIALS; BUILDINGS; CARBON ADDITIONS; CHALCOGENIDES; CHROMIUM ALLOYS; CHROMIUM-NICKEL STEELS; COLLOIDS; CONTAINMENT; CORROSION RESISTANT ALLOYS; DISPERSIONS; HEAT RESISTING ALLOYS; HIGH ALLOY STEELS; IRON ALLOYS; IRON BASE ALLOYS; MATERIALS; NICKEL ALLOYS; OXIDES; OXYGEN COMPOUNDS; SAFETY; SOLS; STAINLESS STEELS; STEELS; TRANSITION ELEMENT COMPOUNDS; URANIUM COMPOUNDS; URANIUM OXIDES; ZIRCONIUM COMPOUNDS
Optional Information
- Notes
- Portions of this document are illegible in microfiche products.
- Secondary number(s)
- CONF-860204--40.