Networking Advanced Experimental Capacities in Operating European Materials Testing Reactors for Qualification of Innovative Nuclear Fuel and Materials: The FIJHOP R&D Program Proposal

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F17%3AN0000116" target="_blank" >RIV/26722445:_____/17:N0000116 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Networking Advanced Experimental Capacities in Operating European Materials Testing Reactors for Qualification of Innovative Nuclear Fuel and Materials: The FIJHOP R&D Program Proposal

Popis výsledku v původním jazyce

Presented at conference IGORR-2017, 4.12.2017 – 8.12.2017, Sydney, Australia. The Jules Horowitz Reactor (JHR) is a Material Testing Reactor under construction at CEA Cadarache in Southern France and foreseen to be in operation by the beginning of the next decade. Operated as an User’s facility at international level, it will promote coupled operation between the operating European MTRs (BR2, HFR, LVR-15, HBWR, MARIA…) for performing multilateral programs associating one or several MTRs and hot cell laboratories for post-irradiation examinations (PIEs). These programs will beneficiate from a strong support of state-of-art models and codes, either for defining the experimental protocol or pre-calculating the sample behaviour, or finally assessing results. This last way has been recognized as essential by the JHR Consortium, which endorsed the objectives of a proposal called FIJHOP (Foundation for future International Jules HOrowitz experimental Programs), submitted to the last H2020 call in October 2016. Supported by some communities such as NUGENIA, it addressed following scientific issues: For nuclear fuels (FIJHOP-F): to discriminate and quantify phenomena having an impact on clad loading and deformation during a power transient: fuel thermal expansion, fuel swelling, fission gas release and volume change at incipient fuel melting. Such final status will be reached with a high burn-up and multiinstrumented experimental fuel rod, For nuclear materials (FIJHOP-M): to study irradiation effects on Internals and more specifically to check effects of the neutron spectrum on damage accumulation kinetics, which may impact their mechanical properties. Associated particular interest is to harmonize interpretation of such evolution versus dpa(displacement per atom). FIJHOP targeted an implementation in 3 European MTRs in operation (BR2, HFR and LVR-15) and 9 Hot Cell Laboratories, and was accompanied by a code benchmarking. Although the proposal was not accepted for the last H2020 call, partners decided to search for other possible tools/frameworks to maintain or even enlarge the objectives of the former FIJHOP proposal. In particular, contacts are in progress with the Nuclear Science Committee (NSC) of the OECD/NEA. This paper presents the FIJHOP proposal, the scientific objectives in relation with stakes for power reactors operation, its innovative feature, and details on both experiments (fuel and materials). It highlights the added value provided by qualified models for optimizing the experiment preparation, and in turn the interest of expected results for participant’s database improvement, development and qualification of their simulation tools.

Název v anglickém jazyce

Networking Advanced Experimental Capacities in Operating European Materials Testing Reactors for Qualification of Innovative Nuclear Fuel and Materials: The FIJHOP R&D Program Proposal

Popis výsledku anglicky

Presented at conference IGORR-2017, 4.12.2017 – 8.12.2017, Sydney, Australia. The Jules Horowitz Reactor (JHR) is a Material Testing Reactor under construction at CEA Cadarache in Southern France and foreseen to be in operation by the beginning of the next decade. Operated as an User’s facility at international level, it will promote coupled operation between the operating European MTRs (BR2, HFR, LVR-15, HBWR, MARIA…) for performing multilateral programs associating one or several MTRs and hot cell laboratories for post-irradiation examinations (PIEs). These programs will beneficiate from a strong support of state-of-art models and codes, either for defining the experimental protocol or pre-calculating the sample behaviour, or finally assessing results. This last way has been recognized as essential by the JHR Consortium, which endorsed the objectives of a proposal called FIJHOP (Foundation for future International Jules HOrowitz experimental Programs), submitted to the last H2020 call in October 2016. Supported by some communities such as NUGENIA, it addressed following scientific issues: For nuclear fuels (FIJHOP-F): to discriminate and quantify phenomena having an impact on clad loading and deformation during a power transient: fuel thermal expansion, fuel swelling, fission gas release and volume change at incipient fuel melting. Such final status will be reached with a high burn-up and multiinstrumented experimental fuel rod, For nuclear materials (FIJHOP-M): to study irradiation effects on Internals and more specifically to check effects of the neutron spectrum on damage accumulation kinetics, which may impact their mechanical properties. Associated particular interest is to harmonize interpretation of such evolution versus dpa(displacement per atom). FIJHOP targeted an implementation in 3 European MTRs in operation (BR2, HFR and LVR-15) and 9 Hot Cell Laboratories, and was accompanied by a code benchmarking. Although the proposal was not accepted for the last H2020 call, partners decided to search for other possible tools/frameworks to maintain or even enlarge the objectives of the former FIJHOP proposal. In particular, contacts are in progress with the Nuclear Science Committee (NSC) of the OECD/NEA. This paper presents the FIJHOP proposal, the scientific objectives in relation with stakes for power reactors operation, its innovative feature, and details on both experiments (fuel and materials). It highlights the added value provided by qualified models for optimizing the experiment preparation, and in turn the interest of expected results for participant’s database improvement, development and qualification of their simulation tools.

Druh

O - Ostatní výsledky

CEP obor

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OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

<a href="/cs/project/LE15024" target="_blank" >LE15024: Umožnění zapojení výzkumných organizací do evropské aliance pro energetický výzkum (European Energy Research Alliance - EERA)</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2017

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů