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International Project on Innovative Nuclear

INTERNATIONAL ATOMIC ENERGY AGENCY, Guidance for the Evaluation of Innovative Nuclear Reactors and Fuel Cycles Report of Phase lA of the International Project on Innovative Nuclear Reactors and Fuel Cycles (INPRO), lAEA-TECDOC-1362, Vienna (2003). [Pg.48]

INPRO in Brief—International Project on Innovative Nuclear Reactcxs and Fuel Cycles, IAEA, 2012 Enhancing Global Nuclear Energy Sustainability (INPRO 40 members in 2014)—www.iaea.org/ INPRO. [Pg.250]

INPRO INternational PROject on Innovative Nuclear Reactors and Fuel Cycles IP Intermediate pressure... [Pg.929]

An Advisory Group Meeting (AGM) on Development of a Strategic Plan for an International R D Project on Innovative Nuclear Fuel Cycles and Power Plants was held in Vienna, 11-14 October 1999. The AGM recommended that the IAEA consider certain candidate projects in support of the development of innovative nuclear power technology, one of which was natural circulation systems. [Pg.249]

The CAREM project involves technological and engineering solutions, as well as several innovative design features that have been properly proved during the design phase. Within CAREM project, the effort was focused mainly on the nuclear island (inside containment and safety systems) where several innovative design solutions require developments. This comprises mainly the reactor core cooling system, the reactor core and fuel assembly, the reactor pressure vessel internals and the hydraulic control rod drive mechanisms. [Pg.118]

XIX-17] ROGOV, M.F., KORNIENKO, A.G, Advanced and innovative projects in the development strategy of concern Rosenergoatom , International Conference on Nuclear Power and Fuel Cycles, CD-ROM, Paper No. 7 Moscow, NIKIET, December 1-2, 2003, (Proc. Conf. Moscow-Dimitrovgrad, Russia, 2003). [Pg.550]

Within CAREM project, the effort has been focused mainly on the nuclear island, i.e. internals of the containment and safety systems, where several innovative design solutions require R D within the first stage, in order to assure that they comply with functional requirements. These are mainly the solutions for Reactor Core Cooling System (RCCS), Reactor Core and Fuel Assembly, Reactor Pressure Vessel Internals (RPVI), and First Shutdown System (FSS). To fulfil project requirements, an extensive experimental plan has been prepared that includes the design and construction of several experimental facilities. [Pg.39]

Abstract The paper presents an overview of the projects of reactor installations with small modular lead-bismuth cooled reactors SVBR-75/100. The R D performed in the Russian Federation has demonstrated technical feasibility and potential economic competitiveness of the SVBR-75/100 reactor installations for nuclear power systems of both near and far future. In its present design, the reactor implements a conservative approach thoroughly based on 80 reactor-year experience in the operation of small lead-bismuth cooled reactors for nuclear submarines. Further on, upon construction and successful operation of an SVBR-75/100 demonstration prototype, more innovative approaches to reactor design could be gradually validated and implemented. Modular structure of nuclear steam supply system of a power unit with SVBR-75/100 reactor installations makes it possible to reduce the NPP construction period and, in the future, to make a transfer to standardized design of power units of different capacity on the basis of serially produced reactor modules. Such approach would assure competitiveness of the NPPs not only in electricity markets but in investment markets as well. It is shown efficient to use SVBR-75/100 reactor installations for renovation of the second unit of the Novovoronezhskaya NPP in the Russian Federation. It could also be envisaged that SVBR-75/100, a reactor that meets the requirements to nuclear power systems of the 2U century, will provide a basis for launching collaborative international project. [Pg.159]

Along with the designs based on proven reactor technologies, some innovative concepts of small reactors that meet the definition of a nuclear battery - power source for long-time unattended operation - are under development in the Russian Federation. Bringing such concepts to practical realization requires a substantial amount of R D to be performed and a demonstration prototype to be created. The important tool for speeding-up the development of such concepts may be international cooperation coordinated by the IAEA, e.g. within its INPRO project. [Pg.122]


See other pages where International Project on Innovative Nuclear is mentioned: [Pg.119]    [Pg.1]    [Pg.6]    [Pg.131]    [Pg.108]    [Pg.119]    [Pg.1]    [Pg.6]    [Pg.131]    [Pg.108]    [Pg.6]    [Pg.5]    [Pg.280]    [Pg.17]    [Pg.50]    [Pg.250]    [Pg.638]   


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