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  2. Pressurized heavy-water reactor - Wikipedia

    en.wikipedia.org/.../Pressurized_heavy-water_reactor

    A pressurized heavy-water reactor (PHWR) is a nuclear reactor that uses heavy water (deuterium oxide D 2 O) as its coolant and neutron moderator. [1] PHWRs frequently use natural uranium as fuel, but sometimes also use very low enriched uranium .

  3. Economics of nuclear power plants - Wikipedia

    en.wikipedia.org/wiki/Economics_of_nuclear_power...

    [115] [116] Also in 2020, the Energy Impact Center, a Washington, D.C. based research institute founded by Bret Kugelmass, introduced the OPEN100 project, a platform that provides open-source blueprints for a nuclear plant with a pressurized water reactor. The OPEN100 model could be used to build a plant for $300 million in two years. [114]

  4. IPHWR-700 - Wikipedia

    en.wikipedia.org/wiki/IPHWR-700

    Like other pressurized heavy-water reactors, IPHWR-700 uses heavy water (deuterium oxide, D 2 O) as its coolant and neutron moderator. The design retains the features of other standardized Indian PHWR units, which include: [4] Two diverse and fast acting shutdown systems; Double containment of reactor building; A water filled calandria vault

  5. A: So the reactor is fueled, the reactor is closed, bolted shut. Control rods are slowly being pulled out. The control rods absorb neutrons without undergoing any nuclear reactions.

  6. Nuclear reactor - Wikipedia

    en.wikipedia.org/wiki/Nuclear_reactor

    Some reactors have been cooled by heavy water which also served as a moderator. Examples include: Early CANDU reactors (later ones use heavy water moderator but light water coolant) DIDO class research reactors; Liquid metal cooled reactor. Since water is a moderator, it cannot be used as a coolant in a fast reactor.

  7. IPHWR - Wikipedia

    en.wikipedia.org/wiki/IPHWR

    The IPHWR (Indian Pressurized Heavy Water Reactor) is a class of Indian pressurized heavy-water reactors designed by the Bhabha Atomic Research Centre. [1] The baseline 220 MWe design was developed from the CANDU based RAPS-1 and RAPS-2 reactors built at Rawatbhata , Rajasthan.

  8. Advanced heavy-water reactor - Wikipedia

    en.wikipedia.org/wiki/Advanced_heavy-water_reactor

    The advanced heavy-water reactor (AHWR) or AHWR-300 is the latest Indian design for a next-generation nuclear reactor that burns thorium in its fuel core. It is slated to form the third stage in India's three-stage fuel-cycle plan. [1] This phase of the fuel cycle plan was supposed to be built starting with a 300 MWe prototype in 2016. [2]

  9. Steam generator (nuclear power) - Wikipedia

    en.wikipedia.org/wiki/Steam_generator_(nuclear...

    In other types of reactors, such as the pressurised heavy water reactors of the CANDU design, the primary fluid is heavy water. Liquid metal cooled reactors such as the Russian BN-600 reactor use a liquid metal, such as sodium, as the primary coolant. These also use heat exchangers between primary metal coolant and the secondary water coolant ...