Published May 2020
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Simulation of Molten Core Concrete Interaction for CANDU Accident Late Phase by MEDICIS Module
Description
Model of Erosion Due to Interaction of CorIum with basement Substance: MEDICIS contains: - A model of the structure of the corium concrete interface; - Models of corium coolability in case of water injection upon the corium pool surface; - Models of evolution of corium pool configuration; - Models to evaluate the release from the ex-vessel corium pool of concrete aerosols and the release of fission products during MCCI; - interface with the physico-chemistry MDB package (Material Data Bank), to evaluate the corium layers properties.
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51089943.pdf
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Additional details
Identifiers
Publishing Information
- ISBN
- 978-92-0-106320-5
- Imprint Title
- In-vessel Melt Retention and Ex-vessel Corium Cooling. Summary of a Technical Meeting. Supplementary Files
- Imprint Pagination
- vp.
- Journal Page Range
- 25 p.
- ISSN
- 1011-4289
- Report number
- IAEA-TECDOC--1906(SUPPLEMENTARY FILES)
Conference
- Title
- Technical Meeting on Phenomenology and Technologies Relevant to In-Vessel Melt Retention and Ex-Vessel Corium Cooling
- Dates
- 17-21 Oct 2016
- Place
- Shanghai (China)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 51089943
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AEROSOLS; BASEMENTS; CANDU TYPE REACTORS; CHEMISTRY; CONFIGURATION; CORIUM; EROSION; FISSION PRODUCT RELEASE; LAYERS; MOLTEN CORE-CONCRETE INTERACTIONS; PONDS; REACTOR ACCIDENTS; SIMULATION; SURFACES
- Descriptors DEC
- ACCIDENTS; COLLOIDS; DISPERSIONS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; REACTORS; SOLS; SURFACE WATERS; THERMAL REACTORS