Published May 2020 | Version v1
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Simulation of Molten Core Concrete Interaction for CANDU Accident Late Phase by MEDICIS Module

  • 1. Institute for Nuclear Research, Pitesti (Romania)

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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Part of:
In-vessel Melt Retention and Ex-vessel Corium Cooling. Summary of a Technical Meeting. Supplementary Files

Additional details

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

Optional Information