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  2. Pressurized heavy-water reactor - Wikipedia

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

    The heavy water coolant is kept under pressure to avoid boiling, allowing it to reach higher temperature (mostly) without forming steam bubbles, exactly as for a pressurized water reactor (PWR). While heavy water is very expensive to isolate from ordinary water (often referred to as light water in contrast to heavy water), its low absorption of ...

  3. 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

  4. 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.

  5. Mitsubishi APWR - Wikipedia

    en.wikipedia.org/wiki/Mitsubishi_APWR

    The Mitsubishi advanced pressurized water reactor (APWR) is a generation III nuclear reactor design developed by Mitsubishi Heavy Industries (MHI) based on pressurized water reactor technology. It features several design enhancements including a neutron reflector, improved efficiency and improved safety systems. It has safety features advanced ...

  6. Pressurized water reactor - Wikipedia

    en.wikipedia.org/wiki/Pressurized_water_reactor

    Due to the requirement to load a pressurized water reactor's primary coolant loop with boron, undesirable radioactive secondary tritium production in the water is over 25 times greater than in boiling water reactors of similar power, owing to the latter's absence of the neutron moderating element in its coolant loop. The tritium is created by ...

  7. IPHWR-220 - Wikipedia

    en.wikipedia.org/wiki/IPHWR-220

    The IPHWR-220 (Indian Pressurized Heavy Water Reactor-220) is an Indian pressurized heavy-water reactor designed by the Bhabha Atomic Research Centre. [1] It is a Generation II reactor developed from earlier CANDU based RAPS-1 and RAPS-2 reactors built at Rawatbhata, Rajasthan. It can generate 220 MW of electricity.

  8. Pressurizer (nuclear power) - Wikipedia

    en.wikipedia.org/wiki/Pressurizer_(nuclear_power)

    Water pressure in a closed system tracks water temperature directly; as the temperature goes up, pressure goes up and vice versa. To increase the pressure in the reactor coolant system, large electric heaters in the pressurizer are turned on, raising the coolant temperature in the pressurizer and thereby raising the pressure. To decrease ...

  9. IPWR-900 - Wikipedia

    en.wikipedia.org/wiki/IPWR-900

    The Indian Pressurized Water Reactor-900 (IPWR-900) is a class of pressurized water reactors being designed by the Bhabha Atomic Research Centre (BARC) in partnership with the Nuclear Power Corporation of India Limited to supplement the Indian three-stage nuclear power programme.