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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

    Heavy Water Secondary coolant material Light Water Moderator material Heavy Water Reactor operating pressure, kg/cm 2 (g) 87 100 100 Active core height, cm 508.5 594 594 Equivalent core diameter, cm 451 – 638.4 Average fuel power density 9.24 KW/KgU 235 MW/m 3: Average core power density, MW/m 3: 10.13 12.1 Fuel Sintered Natural UO 2 pellets

  4. Heavy water - Wikipedia

    en.wikipedia.org/wiki/Heavy_water

    Heavy water is less dissociated than light water at given temperature, and the true concentration of D + ions is less than H + ions would be for light water at the same temperature. The same is true of OD − vs. OH − ions. For heavy water Kw D 2 O (25.0 °C) = 1.35 × 10 −15, and [D + ] must equal [OD − ] for neutral water

  5. Light-water reactor - Wikipedia

    en.wikipedia.org/wiki/Light-water_reactor

    The light-water reactor (LWR) is a type of thermal-neutron reactor that uses normal water, as opposed to heavy water, as both its coolant and neutron moderator; furthermore a solid form of fissile elements is used as fuel. Thermal-neutron reactors are the most common type of nuclear reactor, and light-water reactors are the most common type of ...

  6. Generation III reactor - Wikipedia

    en.wikipedia.org/wiki/Generation_III_reactor

    The Advanced CANDU Reactor is a hybrid CANDU design that retains the heavy water moderator but replaces the heavy water coolant with conventional light water coolant, significantly reducing heavy water costs compared to traditional CANDU designs but losing the characteristic CANDU capability of using unenriched natural uranium as fuel. BARC ...

  7. Steam-Generating Heavy Water Reactor - Wikipedia

    en.wikipedia.org/wiki/Steam-Generating_Heavy...

    The Steam Generating Heavy Water Reactor (SGHWR) was a United Kingdom design for commercial nuclear reactors. It uses heavy water as the neutron moderator and normal "light" water as the coolant. The coolant boils in the reactor, like a boiling water reactor, and drives the power-extraction steam turbines. A single prototype of the design, the ...

  8. GE Hitachi Nuclear Energy - Wikipedia

    en.wikipedia.org/wiki/GE_Hitachi_Nuclear_Energy

    GE and Hitachi have developed the world’s safest Boiling Water Reactors (BWRs) over 60 years, with 40 reactors operating in 5 countries. BWRs and Pressurized Water Reactors (PWRs) both use light water as coolant and steam source, but BWRs generate steam directly in the reactor core, while PWRs use a secondary loop to produce steam. [24]

  9. 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.