REDUCTION OF RADIOLOGICAL CONSEQUENCES OF DESIGN BASIS AND DESIGN EXTENDION ACCIDENTS

Informations projet

R2CA

N° de convention de subvention: 847656

DOI

10.3030/847656

Projet clôturé

Date de signature de la CE 24 Mai 2019

Date de début 1 Septembre 2019

Date de fin 31 Decembre 2023

Financé au titre de

• Euratom

Coût total

€ 4 156 896,25

Contribution de l’UE

€ 3 184 940,82

Coordonné par

INSTITUT DE RADIOPROTECTION ET DE SURETE NUCLEAIRE
France

CORDIS fournit des liens vers les livrables publics et les publications des projets HORIZON.

Les liens vers les livrables et les publications des projets du 7e PC, ainsi que les liens vers certains types de résultats spécifiques tels que les jeux de données et les logiciels, sont récupérés dynamiquement sur OpenAIRE .

Livrables

Documents, reports (22)

Minutes of the Senior Expert Group meeting

Minutes of the Senior Expert Group meeting identifying explicitely the reactor configuration to be analyzed during the project

Minutes of the kick-off meeting

D1.1 Minutes of the kick-off meeting

LOCA and SGTR available simulation codes

Report describing the existing simulation codes used for different kinds of reactors (PWR, VVER...) for LOCA and SGTR transients for both DBA and DEC-A conditions

Report on Pro and Cons of innovative devices and management approaches

Report gathering the selection of the most promising innovative devices and approaches applicable for managing LOCA and SGTR transients in both DBA and DEC-A domains, discussing the quantification of gains by comparing to the actual prescribed Emergency Operating Procédures.

Final report on rod cladding failure during LOCA

Final report on experimental database reassessment including an enlargement of the existing database with past private burst tests and various pellet and clad materials and on model and code improvements for what concerns rod cladding failure during LOCA

Final report on rod cladding failure during SGTR

Progress report on model and code improvements for what concerns the rod cladding failure during a SGTR transient adressing the defective fuel rods and the formation of secondary defects in the cladding due to internal hydriding

LOCA and SGTR available experimental data

Report describing the available experimental data that can be used for LOCA and SGTR transients both in DBA and DEC-A conditions

Final report on fission product relase during LOCA

Final report on experimental database reassessment and on models and code improvements for what concerns the fission product behaviour during their transport in the primary circuit and the reactor containment

LOCA and SGTR DBA and DEC-A available evaluation methodologies

Report describing the existing evaluation methodologies for LOCA and SGTR transients for both DBA and DEC-A conditions

Final report on fission product release during SGTR

Final report on experimental database reassessment and on model and code improvements for what concerns the fission product release and transport during a SGTR transient focusing on the iodine behaviour in the primary circuit at high temperature and pressure

Quality Management report

Report describing the quality standards and acitions that will be used during the project

Second yearly activity report

Report summarizing the main results and outcomes of the Project achieved during the second year and describing the partner's activities per Work-Packages

Report on innovative diagnosis tools and devices

Report on innovative diagnosis tools and devices using both the most recent statistical approaches for the post-processing data issued from the monitored normal operation and transients and artificial intelligence methods to learn the inference between postulated variables of the fuel rod defects and variables of the primary circuit activity evolution.

Failure criteria for defective fuel rods during SGTR

Proposals for defective fuel rod failure criteria in presence of a secondary hydride region incuding a statistical methodology for the evaluation of the defective rod failure in normal conditions

Uncertainty analyses

Report gathering the main results of the uncertainty analyses using mathematical statistical Tools to determine an envelope of the possible code results It will adress uncertainties due to code models as well as uncertainties due to scaling effects

Reassessment of reactor tests cases

Report gathering the main results of the different reactor test case simulations on the basis of the identifying scenarios by the SEG and using an improved version of the calculation schemes and enhanced code versions

First yearly activity report

Report summarizing the main results and outcomes of the Project achieved during the first year and describing the partner's activities per Work-Packages

Report on Pro and Cons of ATF

Report on evaluation of some promising Accident Tolerant Fuels in light of the project results and notably of the methodologies and calculation schemes proposed in WP2 particuliarly targeting the DEC-A conditions

Final report on fuel rod behaviour during LOCA

Final report on experimental database reassessment and on model and code improvements for what concerns the complex fuel behaviour during a LOCA transient Proposals for enhanced models in mechanistic tools and in fuel performance codes

Final project synthesis activity report

Report summarizing the main results and outcomes of the Project achieved during its overall duration

Third yearly activity report

Report summarizing the main results and outcomes of the Project achieved during the third year and describing the partners activities per WorkPackages

Updated harmonized methodologies

Report describing new simulation stratégies and best practices and proposing harmonized evaluation methodologies

Open Research Data Pilot (2)

Data Management Plan

Report describing the management of the data produced during the project within and outside the consortium

R2CA public website

Creation of the public part of the R2CA website that will be also used for WP1 activities

Publications

Other (10)

Final Report on innovative diagnosis tools and devices

Auteurs: W. Giannotti and al.
Publié dans: 2023
Éditeur: zenodo
DOI: 10.5281/zenodo.10798166

Fianl report on fission product releases and transport during LOCA

Auteurs: A. Kecek and al.
Publié dans: 2023
Éditeur: zenodo
DOI: 10.5281/zenodo.10797786

R2CA 4th Newsletter

Auteurs: N. Girault
Publié dans: 2024
Éditeur: zenodo
DOI: 10.5281/zenodo.10797740

Final report on rod cladding failure due to secondary hydriding

Auteurs: C. Leclere and al.
Publié dans: 2023
Éditeur: zenodo
DOI: 10.5281/zenodo.10798156

R2CA third yearly Activity report

Auteurs: N. Girault and al.
Publié dans: 2023
Éditeur: zenodo
DOI: 10.5281/zenodo.10796982

Rod cladding failure during LOCA- Final report on experimental database reassessment and model/code improvements

Auteurs: T. Taurines and al.
Publié dans: 2023
Éditeur: zenodo
DOI: 10.5281/zenodo.10798218

Final Report on experimental database reassessment and on model/code improvements for fission product releases during a SGTR transient.

Auteurs: L.E. Herranz
Publié dans: 2023
Éditeur: zenodo
DOI: 10.5281/zenodo.10798088

Fission product release from defective fuel rod during SGTR transient

Auteurs: G. Zullo and al.
Publié dans: 2023
Éditeur: zenodo
DOI: 10.5281/zenodo.10798136

Report on innovative diagnosis tools and devices

Auteurs: K. Chevalier-Jabet and al.
Publié dans: 2023
Éditeur: zenodo
DOI: 10.5281/zenodo.10798192

R2CA first Newsletter

Auteurs: N. Girault
Publié dans: 2020
Éditeur: zenodo
DOI: 10.5281/zenodo.5222766

Peer reviewed articles (12)

Defective PWR fuel rods detection and characterisation using an Artificial Neural Network

Auteurs: L. Verma, F. Kremer, K. Chevalier-Jabet
Publié dans: Progress in Nuclear Energy, Numéro 160, 2023, Page(s) 104686, ISSN 0149-1970
Éditeur: Elsevier BV
DOI: 10.1016/j.pnucene.2023.104686

The SCIANTIX code for fission gas behaviour: Status, upgrades, separate-effect validation, and future developments

Auteurs: G. Zullo, D. Pizzocri, L. Luzzi
Publié dans: Journal of Nuclear Materials, Numéro 587, 2023, Page(s) 154744, ISSN 0022-3115
Éditeur: Elsevier BV
DOI: 10.1016/j.jnucmat.2023.154744

Towards simulation of fuel rod behaviour during severe accidents by coupling TRANSURANUS with SCIANTIX and MFPR-F

Auteurs: G. Zullo, D. Pizzocri, L. Luzzi, F. Kremer, R. Dubourg, A. Schubert, P. van Uffelen
Publié dans: Annals of Nuclear Energy, Numéro 190, 2023, Page(s) 109891, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.109891

Iodine source term assessment under DBA SGTR accident scenario

Auteurs: A. Bousbia Salah, M. Di Giuli, P. Foucaud, R. Iglesias, A. Malkhasyan, M. Salmaoui, L.E. Herranz
Publié dans: Annals of Nuclear Energy, Numéro 196, 2024, Page(s) 110201, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.110201

Towards preliminary design calculations with TRANSURANUS for application of Hastelloy cladding material

Auteurs: A. de Lara, A. Schubert, E. Shwageraus, P. Van Uffelen
Publié dans: Annals of Nuclear Energy, Numéro 192, 2023, Page(s) 109973, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.109973

Iodine source term assessment as result of iodine spiking and mass transfer phenomena during a SGTR transient using MELCOR 2.2 and CATHARE 2 codes

Auteurs: P. Foucaud, M. di Giuli, M. Salmaoui, A. Bousbia Salah, R. Iglesias, A. Malkhasyan, L.E. Herranz
Publié dans: Annals of Nuclear Energy, Numéro 198, 2024, Page(s) 110305, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.110305

Assessment of hydride precipitation modelling across fuel cladding: Hydriding in non-defective and defective fuel rods

Auteurs: F. Feria, L.E. Herranz
Publié dans: Annals of Nuclear Energy, Numéro 188, 2023, Page(s) 109810, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.109810

Towards modelling defective fuel rods in TRANSURANUS: Benchmark and assessment of gaseous and volatile radioactive fission product release

Auteurs: L. Giaccardi, M. Cherubini, G. ZUllo, D. Pizzocri, A. Magni, L. Luzzi
Publié dans: Annals of Nuclear Energy, Numéro 197, 2024, Page(s) 110249, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.110249

Assessment of cladding ballooning during DBA-LOCAs with FRAPTRAN

Auteurs: F. Feria, P. Aragon, L.E. Herranz
Publié dans: Annals of Nuclear Energy, Numéro 195, 2024, Page(s) 110194, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.110194

Methods for the radioactive release estimation under DEC-A conditions

Auteurs: T. Kaliatka, T. Kacegavicius; A. Kaliatka, M. Povilaitis, A. Tidikas, A. Slavickas
Publié dans: Annals of Nuclear Energy, Numéro 195, 2023, Page(s) 110143, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.110143

Towards grain-scale modelling of the release of radioactive fission gas from oxide fuel. Part II: Coupling SCIANTIX with TRANSURANUS

Auteurs: G. Zullo, D. Pizzocri, A. Magni, P. Van Uffelen, A. Schubert, L. Luzzi
Publié dans: Nuclear Engineering and Technology, Numéro 54, 2022, Page(s) 4460, ISSN 1738-5733
Éditeur: Korean Nuclear Society
DOI: 10.1016/j.net.2022.07.018

Conservative evaluation of radionuclides release for VVER-440 and VVER-1000 type reactors

Auteurs: A. Berezhnyi, A. Krushynskyi, D. Ruban, S. Sholomitsky
Publié dans: Annals of Nuclear Energy, Numéro 194, 2023, Page(s) 110105, ISSN 0306-4549
Éditeur: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.110105