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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 ...
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
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
The Douglas Point Nuclear Generating Station was Canada’s first full-scale nuclear power plant and the second CANDU (CANada Deuterium Uranium) pressurised heavy water reactor. Its success was a major milestone and marked Canada's entry into the global nuclear power scene. The same site was later used for the Bruce Nuclear Generating Station.
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]
Overall, CANDU reactors use 30–40% less mined uranium than light-water reactors per unit of electricity produced. This is a major advantage of the heavy-water design; it not only requires less fuel, but as the fuel does not have to be enriched, it is much less expensive as well.
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.
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 ...