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  2. TerraPower - Wikipedia

    en.wikipedia.org/wiki/TerraPower

    In October 2020, the company was chosen by the United States Department of Energy as a recipient of a matching grant totaling between $400 million and $4 billion over the ensuing 5 to 7 years to build a demonstration reactor using their "Natrium" design. Natrium uses liquid sodium as a coolant (reducing the cost using an ambient pressure ...

  3. Hallam Nuclear Power Facility - Wikipedia

    en.wikipedia.org/wiki/Hallam_Nuclear_Power_Facility

    The sodium-cooled graphite-moderated reactor (SGR) design (of which HNFP was a demonstration) targeted economical commercial nuclear electricity. The liquid metal coolant enabled operation at temperatures sufficiently high to produce steam conditions identical to those used in fossil-fueled power plants, enhancing power conversion efficiency ...

  4. Sodium-cooled fast reactor - Wikipedia

    en.wikipedia.org/wiki/Sodium-cooled_fast_reactor

    A sodium-cooled fast reactor is a fast neutron reactor cooled by liquid sodium. The initials SFR in particular refer to two Generation IV reactor proposals, one based on existing liquid metal cooled reactor (LMFR) technology using mixed oxide fuel (MOX), and one based on the metal-fueled integral fast reactor .

  5. CFR-600 - Wikipedia

    en.wikipedia.org/wiki/CFR-600

    The CFR-600 (Xiapu fast reactor pilot project) is a sodium-cooled pool-type fast-neutron nuclear reactor under construction in Xiapu County, Fujian province, China, on Changbiao Island. [1] [2] It is a generation IV demonstration project by the China National Nuclear Corporation (CNNC). Construction started in late 2017.

  6. ASTRID (reactor) - Wikipedia

    en.wikipedia.org/wiki/ASTRID_(reactor)

    ASTRID (Advanced Sodium Technological Reactor for Industrial Demonstration) was a proposal for a 600 MW sodium-cooled fast breeder reactor (Generation IV), proposed by the Commissariat à l'énergie atomique (CEA). It was to be built on the Marcoule Nuclear Site in France.

  7. Fast Flux Test Facility - Wikipedia

    en.wikipedia.org/wiki/Fast_Flux_Test_Facility

    The Fast Flux Test Facility (FFTF) is a 400 MW thermal, liquid sodium cooled, nuclear test reactor owned by the U.S. Department of Energy. It does not generate electricity. It is situated in the 400 Area of the Hanford Site, which is located in the state of Washington.

  8. Experimental Breeder Reactor II - Wikipedia

    en.wikipedia.org/wiki/Experimental_Breeder...

    The tube is welded shut at the top to form a unit 73 cm (29 in) long. The purpose of the sodium is to function as a heat-transfer agent. As more and more of the uranium undergoes fission, it develops fissures and the sodium enters the voids. It extracts an important fission product, caesium-137, and hence becomes intensely radioactive.

  9. Kilopower - Wikipedia

    en.wikipedia.org/wiki/Kilopower

    Kilopower is an experimental U.S. project to make new nuclear ... demonstration reactor were ... which means that liquid sodium can flow freely at high temperatures ...