23 research outputs found

    Origine et développement du combustible Uranium-Molybdène (U-Mo)

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    Historiquement, la plupart des réacteurs expérimentaux, en particulier les Réacteurs de Test et de Recherche, producteurs de hauts flux neutroniques, ont utilisé du combustible métallique à haut enrichissement en U235 (>90%). La politique actuelle est de plafonner l'enrichissement en U235 à 20% (objectif de non-prolifération). Après une première génération de combustible enrichi à 19.75% en U235 de type siliciure non retraitable, un consensus s'est dégagé au niveau international autour d'une nouvelle génération de combustible enrichi à 19.75% en U235, le combustible U-Mo (uranium - molybdène). Ce combustible permet de maintenir, voire d'améliorer, les performances actuelles des réacteurs tout en garantissant une fin de cycle acceptable (combustible retraitable). CEA, COGEMA, CERCA, FRAMATOME et TECHNICATOME ont regroupé leurs moyens techniques, financiers et leur savoir-faire pour développer en commun ce nouveau combustible U-Mo. Il est destiné aux réacteurs existants déjà convertis ou devant se convertir à l'uranium faiblement enrichi (en France, en Allemagne, au Japon, en Suède, ...) ainsi qu'aux nouveaux réacteurs tels que le RJH en France ou RRR en Australie. Ce programme de R& D démarré en 1999 est conduit en cohérence avec les travaux réalisés aux USA par l'Argonne National Laboratory. Compte tenu de la nécessité impérieuse pour les réacteurs de disposer en 2006 de ce nouveau combustible, seul à offrir une véritable solution de fin de cycle, l'objectif du groupe U-Mo français est de terminer la R& D et la qualification du combustible en 2005

    The collaboration of japan and france on the design of astrid sodium fast reactor

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    International audienceSince the beginning (2010), the management of ASTRID project was organized around a strong involvement of industrial partners in the reactor design. The ASTRID project has now entered into its Basic Design phase (duration from year 2016 to 2019) with fourteen industrial partners. Since 2014, a partnership with Japanese nuclear institutes and industries is effective on two main items ASTRID reactor design studies and RetD in support of Sodium Fast Reactors (SFR). This French-Japanese collaboration on ASTRID Program and Sodium Fast Reactor has been set up in two steps the signature of a General Arrangement between CEA and the representatives of MEXT and METI on May 5th, 2014; and in a second step, an Implementing Arrangement signed the same year on August 7th by CEA, AREVA NP, JAEA, MHI and MFBR.This collaboration of a significant level is foreseen to run at least up to the end of 2019. At the beginning, the collaborative work (input data, planning and deliverables) was divided in 29 Task Sheets covering ASTRID design (3 Task Sheets) and RetD (26 Tasks Sheets). Since 2016, the contribution of JAEA/MHI MFBR to the ASTRID reactor engineering studies has significantly raised, passing from 3 to 9 Design Task Sheets. Thus, even if the cooperation is recent, the cooperation between CEA, AREVA NP, JAEA, MHI-MFBR is fruitful and it has been planned by all parties to enlarge Japanese contribution to a process called Joint Evaluation to prepare future Joint Design.This paper aims at the overview of the significant involvement of JAEA/MHI MFBR in the ASTRID design studies through these 9 Task Sheets, covering in particular the design of an active decay heat removal system, and of a passive reactor shutdown system based on a Curie point electromagnet system. MHI / MFBR teams are also implies in fabricability studies of complex component such as the Above Core Structure or the Polar Table. In addition the new Task Sheets are now focusing on thermal-hydraulic and thermomechanical studies related to the primary vessel.Japan contribution to ASTRID program is significant and important. Except CEA (which act as the industrial architect of the project), JAEA-MHI-MFBR became in 2015 the 2nd largest contributor to ASTRID program - behind AREVA NP - in terms of involved staff and financial contribution. It means that ASTRID project has to adapt its project management to cope with this important partnership. The related innovative project organization will be presented too

    Astrid project, from conceptual to basic design progress status

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    International audienceSince the beginning of this year, after 6 years of conceptual design phase, the French 600 eMW ASTRID project has started a 4 years basic design phase. The ASTRID project is funding for basic design phase (2016-2019) through France Future Investments Program. All the Industrials partners involved in the project during the last phase have decided to pursue in the ASTRID project, and the strategic partnership with Japan is going to be reinforced. This very efficient industrial network with CEA as contracting authority is an original and effective project management. Very high level and up-to-date project management methods are performed, including technical control with engineering System tools and 3D mock-up consolidation. On the technical point of view, the first ten months have been kept for a reopening options phase called P2C (Configuration Confirmation Phase) concluded by a configuration review in October. According to conclusions of conceptual design phases, several items had been checked and challenged through three main drivers safety, cost killing and operability. Global consistency was also watched over.It has been also decided for the next two years, to investigate and integrate Gas Power Conversion System in the basic design configuration. The objective for the ASTRID project is to raise Gas PCS integration studies at the same level that was achieved for Water/steam PCS at the end of 2015. A go-no go decision for Gas PCS integration will be organized at the end of 2017.In the same time an ongoing effort started two years ago is underway to map all the qualification needs and define all joined processes consistent with safety regulator requirement. A more realistic planning has been prepared, adding a four years consolidation phase between basic design and detailed design, in order to increase the level of confidence and progress on the technology feasibility including experimental validations of the ASTRID's main innovative options

    Status of the astrid sodium fast reactor project from conceptualdesign to basic design phase

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    International audienceThe ASTRID project is pursuing its progress and has reached at the end of 2015 the Conceptual Design phasefollowed by the starting of the Basic Design phase from 2016 to 2019.The transition from the Conceptual Design phase (2010-2015) to the Basic Design phase (2016-2019) was validated by theproduction of the Conceptual Design files. According to the production of this report, at the end of the Conceptual Designphase (December 2015), the French ministries representatives agreed to launch the Basic Design Phase due to the goodprogression of the program all the milestones have been met during the Conceptual Design phase, and relevant innovationshave been proposed in order to propose a technological demonstration reactor that could fulfilled Generation IV objectives.For the Basic Design phase, the ASTRID project has consolidated its industrial partnership with fourteen industrial partnersespecially strengthened with JAEA / MHI MFBR.The Basic Design phase started with a particular step named Confirmation Configuration Phase (P2C) where during the firstnine months of the 2016 year, the project - with all partners has- re-analyzed several structural options regarding three main drivers safety, operability and cost killing,- implemented the Gas (Nitrogen) Energy Conversion system within the plant design,- and built a coherent reactor layout shared by all partners as a starting point of a new ASTRID configuration forthe Basic Design phase.Therefore, this papers aims at presenting the recent progress of the ASTRID project either in terms of project managementand organization, than in terms of technological progress in reactor design and support studies
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