REDUCTION OF RADIOLOGICAL CONSEQUENCES OF DESIGN BASIS AND DESIGN EXTENDION ACCIDENTS

Risultati finali

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

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

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

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

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

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

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

Pubblicazioni

Final Report on innovative diagnosis tools and devices

Autori: W. Giannotti and al.
Pubblicato in: 2023
Editore: zenodo
DOI: 10.5281/zenodo.10798166

Fianl report on fission product releases and transport during LOCA

Autori: A. Kecek and al.
Pubblicato in: 2023
Editore: zenodo
DOI: 10.5281/zenodo.10797786

R2CA 4th Newsletter

Autori: N. Girault
Pubblicato in: 2024
Editore: zenodo
DOI: 10.5281/zenodo.10797740

Final report on rod cladding failure due to secondary hydriding

Autori: C. Leclere and al.
Pubblicato in: 2023
Editore: zenodo
DOI: 10.5281/zenodo.10798156

R2CA third yearly Activity report

Autori: N. Girault and al.
Pubblicato in: 2023
Editore: zenodo
DOI: 10.5281/zenodo.10796982

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

Autori: T. Taurines and al.
Pubblicato in: 2023
Editore: 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.

Autori: L.E. Herranz
Pubblicato in: 2023
Editore: zenodo
DOI: 10.5281/zenodo.10798088

Fission product release from defective fuel rod during SGTR transient

Autori: G. Zullo and al.
Pubblicato in: 2023
Editore: zenodo
DOI: 10.5281/zenodo.10798136

Report on innovative diagnosis tools and devices

Autori: K. Chevalier-Jabet and al.
Pubblicato in: 2023
Editore: zenodo
DOI: 10.5281/zenodo.10798192

R2CA first Newsletter

Autori: N. Girault
Pubblicato in: 2020
Editore: zenodo
DOI: 10.5281/zenodo.5222766

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

Autori: L. Verma, F. Kremer, K. Chevalier-Jabet
Pubblicato in: Progress in Nuclear Energy, Numero 160, 2023, Pagina/e 104686, ISSN 0149-1970
Editore: Elsevier BV
DOI: 10.1016/j.pnucene.2023.104686

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

Autori: G. Zullo, D. Pizzocri, L. Luzzi
Pubblicato in: Journal of Nuclear Materials, Numero 587, 2023, Pagina/e 154744, ISSN 0022-3115
Editore: 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

Autori: G. Zullo, D. Pizzocri, L. Luzzi, F. Kremer, R. Dubourg, A. Schubert, P. van Uffelen
Pubblicato in: Annals of Nuclear Energy, Numero 190, 2023, Pagina/e 109891, ISSN 0306-4549
Editore: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.109891

Iodine source term assessment under DBA SGTR accident scenario

Autori: A. Bousbia Salah, M. Di Giuli, P. Foucaud, R. Iglesias, A. Malkhasyan, M. Salmaoui, L.E. Herranz
Pubblicato in: Annals of Nuclear Energy, Numero 196, 2024, Pagina/e 110201, ISSN 0306-4549
Editore: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.110201

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

Autori: A. de Lara, A. Schubert, E. Shwageraus, P. Van Uffelen
Pubblicato in: Annals of Nuclear Energy, Numero 192, 2023, Pagina/e 109973, ISSN 0306-4549
Editore: 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

Autori: P. Foucaud, M. di Giuli, M. Salmaoui, A. Bousbia Salah, R. Iglesias, A. Malkhasyan, L.E. Herranz
Pubblicato in: Annals of Nuclear Energy, Numero 198, 2024, Pagina/e 110305, ISSN 0306-4549
Editore: 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

Autori: F. Feria, L.E. Herranz
Pubblicato in: Annals of Nuclear Energy, Numero 188, 2023, Pagina/e 109810, ISSN 0306-4549
Editore: 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

Autori: L. Giaccardi, M. Cherubini, G. ZUllo, D. Pizzocri, A. Magni, L. Luzzi
Pubblicato in: Annals of Nuclear Energy, Numero 197, 2024, Pagina/e 110249, ISSN 0306-4549
Editore: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.110249

Assessment of cladding ballooning during DBA-LOCAs with FRAPTRAN

Autori: F. Feria, P. Aragon, L.E. Herranz
Pubblicato in: Annals of Nuclear Energy, Numero 195, 2024, Pagina/e 110194, ISSN 0306-4549
Editore: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.110194

Methods for the radioactive release estimation under DEC-A conditions

Autori: T. Kaliatka, T. Kacegavicius; A. Kaliatka, M. Povilaitis, A. Tidikas, A. Slavickas
Pubblicato in: Annals of Nuclear Energy, Numero 195, 2023, Pagina/e 110143, ISSN 0306-4549
Editore: 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

Autori: G. Zullo, D. Pizzocri, A. Magni, P. Van Uffelen, A. Schubert, L. Luzzi
Pubblicato in: Nuclear Engineering and Technology, Numero 54, 2022, Pagina/e 4460, ISSN 1738-5733
Editore: Korean Nuclear Society
DOI: 10.1016/j.net.2022.07.018

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

Autori: A. Berezhnyi, A. Krushynskyi, D. Ruban, S. Sholomitsky
Pubblicato in: Annals of Nuclear Energy, Numero 194, 2023, Pagina/e 110105, ISSN 0306-4549
Editore: Pergamon Press Ltd.
DOI: 10.1016/j.anucene.2023.110105

Risultati finali

Pubblicazioni

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