In-Vessel Melt Retention Severe Accident Management Strategy for Existing and Future NPPs

Akronyymi

IVMR

Rahoitetun hankkeen kuvaus

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.
Näytä enemmän

Aloitusvuosi

2015

Päättymisvuosi

2019

Myönnetty rahoitus

Fortum Power and Heat Oy
47 812 €
Participant
FRAMATOME (FR)
24 996 €
Participant
MAGYAR TUDOMANYOS AKADEMIA ENERGIATUDOMANYI KUTATOKOZPONT (HU)
46 000 €
Participant
NUBIKI Nuclear Safety Research Institute Ltd. (HU)
45 375 €
Participant
KARLSRUHER INSTITUT FUER TECHNOLOGIE (DE)
319 937 €
Participant
CENTRUM VYZKUMU REZ SRO (CZ)
80 000 €
Participant
TRACTEBEL ENGINEERING (BE)
7 875 €
Participant
INZINIERSKA VYPOCTOVA SPOLOCNOST TRNAVA S.R.O. (SK)
108 500 €
Participant
GESELLSCHAFT FUR ANLAGEN UND REAKTORSICHERHEIT (GRS) gGmbH (DE)
Participant
HELMHOLTZ-ZENTRUM DRESDEN-ROSSENDORF EV (DE)
96 600 €
Participant
UJV REZ, a. s. (CZ)
663 397 €
Participant
INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAIRE (FR)
840 130 €
Coordinator
INSTITUTE OF NUCLEAR RESEARCH AND NUCLEAR ENERGY - BULGARIAN ACADEMY OF SCIENCES (BG)
41 400 €
Participant
NARODOWE CENTRUM BADAN JADROWYCH (PL)
57 600 €
Participant
NUCLEAR RESEARCH AND CONSULTANCY GROUP (NL)
69 825 €
Participant
LIETUVOS ENERGETIKOS INSTITUTAS (LT)
28 875 €
Participant
ELECTRICITE DE FRANCE (FR)
125 044 €
Participant
AGENZIA NAZIONALE PER LE NUOVE TECNOLOGIE, L'ENERGIA E LO SVILUPPO ECONOMICO SOSTENIBILE (IT)
109 125 €
Participant
KUNGLIGA TEKNISKA HOEGSKOLAN (SE)
1 078 701 €
Participant
JRC -JOINT RESEARCH CENTRE- EUROPEAN COMMISSION (BE)
293 215 €
Participant
COMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVES (FR)
550 682 €
Participant
IMPERIAL COLLEGE OF SCIENCE TECHNOLOGY AND MEDICINE (UK)
58 030 €
Participant

Myönnetty summa

4 831 454 €

Rahoittaja

Euroopan unioni

Rahoitusmuoto

Research and Innovation action

Puiteohjelma

Horizon 2020 Framework Programme

Haku

Ohjelman osa
Euratom (5421)
Support safe operation of nuclear systems (5480)
Support the development and sustainability of nuclear competences at Union level (5482)
Ensure availability and use of research infrastructures of pan_european relevance (5487)
Aihe
Improved safety design and operation of fission reactors (NFRP-01-2014)
Haun tunniste
NFRP-2014-2015

Muut tiedot

Rahoituspäätöksen numero

662157

Tunnistetut aiheet

nuclear safety, nuclear reactors