Published November 1992 | Version v1
Miscellaneous Metadata-only

Improved WECHSL models including zirconium oxidation and its verification by new beta experiments

Creators

  • 1. Kernforschungszentrum Karlsruhe GmbH (Germany). Inst. fuer Angewandte Thermo- und Fluiddynamik

Description

Recently the experimental programs SURC at SNL (USA), ACE at ANL (USA) and BETA at KfK (Germany) have been carried out in order to investigate the phenomena which are likely to occur during the ex-vessel of a core-melt accident, predominantly in the high temperature phase of concrete erosion with high zirconium content of the melt. During this phase of interaction the condensed phase reaction between zirconium and SiO2 is considered to play an important role. On the base of this BETA test series the improved WECHSL code is validated. (orig.)

Part of:
Second OECD (NEA) CSNI specialist meeting on molten core debris-concrete interactions

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. 147-155.
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
25034339
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
Descriptors DEI
BWR TYPE REACTORS; COMPUTERIZED SIMULATION; CONCRETES; EROSION; MELTDOWN; OXIDATION; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; ZIRCONIUM
Descriptors DEC
ACCIDENTS; BUILDING MATERIALS; CHEMICAL REACTIONS; ELEMENTS; 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.