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Proceedings of the Second OECD (NEA) CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions

Abstract

The Second CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions was held at Kernforschungszentrum Karlsruhe, Germany on April 1-3, 1992. The status and progress in this field of severe reactor accidents were discussed from researchers around the world including participants from Russia and the Czech and Slovak Federal Republic. The contributions concentrated on two main topics. The first topic is the 'classical' core debris-concrete interaction, both experimental and theoretical. Integral effects and separate effects were addressed in thermal hydraulics and heat transfer, material interaction, and aerosol release during concrete erosion, with some applications to prototypical nuclear power plants. The second topic gaining more and more interest is the possibility of controlling and ending the erosion of the concrete by spreading of the core melt, and/or achieving coolability by the addition of water. In the final session it was concluded that considerable progress has been made in understanding and modelling the important phenomena. For the first topic a broad and generally sufficient experimental data base is existing, allowing further improvement qualification of the theoretical models which at present give reasonable agreement with the most important experimental data. A validation matrix is recommended for final validation of the codes. With respect to  More>>
Publication Date:
Jul 01, 1992
Product Type:
Technical Report
Report Number:
NEA-CSNI-R-1992-10; KfK-5108
Resource Relation:
Conference: 2. OECD (NEA) CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions, Karlsruhe (Germany), 1-3 Apr 1992; Other Information: Country of input: International Atomic Energy Agency (IAEA)
Subject:
42 ENGINEERING; AEROSOLS; CONCRETES; EROSION; FISSION PRODUCT RELEASE; FORSCHUNGSZENTRUM KARLSRUHE; HEAT TRANSFER; LEADING ABSTRACT; MEETINGS; NEA; NUCLEAR POWER PLANTS; REACTOR ACCIDENTS; SIMULATION; THERMAL HYDRAULICS; VALIDATION
OSTI ID:
21146829
Research Organizations:
Organisation for Economic Co-Operation and Development - Nuclear Energy Agency, Committee on the safety of nuclear installations - OECD/NEA/CSNI, Le Seine Saint-Germain, 12 boulevard des Iles, F-92130 Issy-les-Moulineaux (France)
Country of Origin:
NEA
Language:
English
Other Identifying Numbers:
Other: ISSN 0303-4003; TRN: XN09C0046026303
Availability:
Available from INIS in electronic form
Submitting Site:
INIS
Size:
602 pages
Announcement Date:
Apr 09, 2009

Citation Formats

None. Proceedings of the Second OECD (NEA) CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions. NEA: N. p., 1992. Web.
None. Proceedings of the Second OECD (NEA) CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions. NEA.
None. 1992. "Proceedings of the Second OECD (NEA) CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions." NEA.
@misc{etde_21146829,
title = {Proceedings of the Second OECD (NEA) CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions}
author = {None}
abstractNote = {The Second CSNI Specialist Meeting on Molten Core Debris-Concrete Interactions was held at Kernforschungszentrum Karlsruhe, Germany on April 1-3, 1992. The status and progress in this field of severe reactor accidents were discussed from researchers around the world including participants from Russia and the Czech and Slovak Federal Republic. The contributions concentrated on two main topics. The first topic is the 'classical' core debris-concrete interaction, both experimental and theoretical. Integral effects and separate effects were addressed in thermal hydraulics and heat transfer, material interaction, and aerosol release during concrete erosion, with some applications to prototypical nuclear power plants. The second topic gaining more and more interest is the possibility of controlling and ending the erosion of the concrete by spreading of the core melt, and/or achieving coolability by the addition of water. In the final session it was concluded that considerable progress has been made in understanding and modelling the important phenomena. For the first topic a broad and generally sufficient experimental data base is existing, allowing further improvement qualification of the theoretical models which at present give reasonable agreement with the most important experimental data. A validation matrix is recommended for final validation of the codes. With respect to fission product release during MCCI measurements show that the releases are significantly less than previously estimated. The relatively new topic of melt coolability deserves further investigations which are already underway at different places or international coordinated efforts.}
place = {NEA}
year = {1992}
month = {Jul}
}