Published November 1992
| Version v1
Miscellaneous
Assessment status of the WECHSL-Mod3 code
Creators
- 1. Inst. de Protection et de Surete Nucleaire, CEN Cadarache, Saint-Paul-les-Durance (France)
- 2. Kernforschungszentrum Karlsruhe (Germany)
Description
The predictive capability of the WECHSL-Mod3 code is evaluated on the basis of a significant set of experiments selected from the BETA I, SURC and ACE test matrices. The prediction of concrete erosion is generally in close agreement with data for all corium compositions and concrete types. The modeling of condensed phase chemistry appears as a major contribution to the proper calculation of the tests where Zr oxidation played a role. Some discrepancies observed for the prediction of concrete ablation and melt temperature for the case of oxidic melts are discussed with respect to the modeling of liquidus/solidus temperatures, of melt-concrete heat transfer and of Zr chemistry at very high temperature. (orig.)
Additional details
Publishing Information
- Imprint Title
- Second OECD (NEA) CSNI specialist meeting on molten core debris-concrete interactions
- Imprint Pagination
- 603 p.
- Journal Page Range
- p. 157-171.
- ISSN
- 0303-4003
- Report number
- KFK--5108
Conference
- Title
- 2. OECD (NEA) CSNI specialist meeting on molten core debris-concrete interactions.
- Dates
- 1-3 Apr 1992.
- Place
- Karlsruhe (Germany).
INIS
- Country of Publication
- Germany
- Country of Input or Organization
- Germany
- INIS RN
- 25036992
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Computer Program Description
- Descriptors DEI
- BWR TYPE REACTORS; COMPUTER CODES; COMPUTER PROGRAM DOCUMENTATION; COMPUTERIZED SIMULATION; CONCRETES; CORIUM; HEAT TRANSFER; MELTDOWN; OXIDATION; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; W CODES; ZIRCONIUM
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; CHEMICAL REACTIONS; ELEMENTS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; MATERIALS; METALS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; TRANSITION ELEMENTS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- NEA/CSNI/R--(92)10.