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IVMR

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In-Vessel Melt Retention Severe Accident Management Strategy for Existing and Fu...

In-Vessel Melt Retention Severe Accident Management Strategy for Existing and Future NPPs The stabilization of molten corium is recognised as essential if a safe and stable state is to be reached following a severe accident. Among the possible options, In-Vessel Melt Retention (IVMR) appears as an attractive solution t... ver más

30/11/2019

IRSN

8M€

Presupuesto del proyecto: 8M€

Líder del proyecto

INSTITUT DE RADIOPROTECTION ET DE SURETE NUCL... No se ha especificado una descripción o un objeto social para esta compañía.

TRL 4-5

Fecha límite participación Sin fecha límite de participación.

Ver 21 Participantes

Financiación concedida El organismo FP6 notifico la concesión del proyecto el día 2019-11-30

NFRP-01-2014: Improved safety design and operatio... Scope:Specific challenge: The European Union (EU) has a strong leadership in reactor design and oper...

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Cerrada hace 10 años

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21 Participantes

IRSN

Lider

KTH

N.D. | Participante

IMPERIAL COLLEGE OF SCIENCE...

N.D. | Participante

EDF

N.D. | Participante

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Duración del proyecto: 53 meses Fecha Inicio: 2015-06-01
Fecha Fin: 2019-11-30

Líder del proyecto

INSTITUT DE RADIOPROTECTION ET DE SURETE NUCL... No se ha especificado una descripción o un objeto social para esta compañía.

TRL 4-5

Presupuesto del proyecto 8M€

Fecha límite de participación Sin fecha límite de participación.

Descripción del proyecto The stabilization of molten corium is recognised as essential if a safe and stable state is to be reached following a severe accident. Among the possible options, In-Vessel Melt Retention (IVMR) appears as an attractive solution that would minimize the risks of containment failure (less Hydrogen produced, no corium-concrete interaction), if it can be proved to be feasible.The strategy is already adopted for the VVER 440 type 213 based on thorough research work for the Finnish Loviisa NPP and Hungarian Paks NPP. It is also included in the design of some new Gen.III reactors like AP-1000, APR 1400 and Chinese CPR-1000. It has also been studied in the past for other reactor concepts like KERENA (BWR) or VVER-640.Current approaches for reactors with relatively small power, such as VVER 440 or AP600, use conservative assumptions. However, for higher power reactors (around 1000 MWe), it is necessary to evaluate the IVMR strategy with best-estimate methods in order to address the uncertainties associated with the involved phenomena. Additional R&D is needed to ensure and demonstrate adequate safety margins, including identification of efficient technical solutions for the external cooling of the vessel and performing best-estimate evaluation of relevant scenarios. Among other provisions, the possibility of cooling the corium inside the vessel by direct injection of water into the degraded core, may be considered because it is likely to remove a significant part of the residual power.The goal of the project is an analysis of the applicability and technical feasibility of the IVMR strategy to high power reactors, both for existing ones (e.g. VVER 1000 type 320 units) as well as for future reactors of different types (PWR or BWR). The main outcomes of the project will be elevant assumptions and scenarios to estimate the maximum heat load on the vessel wall, improved numerical tools for the analysis of IVMR issues and a harmonized methodology on the IVMR.

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