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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 ...
It is used in pressurized water reactors (PWRs), between the primary and secondary coolant loops. It is also used in liquid metal cooled reactors (LMRs), pressurized heavy-water reactors (PHWRs), and gas-cooled reactors (GCRs). In typical PWR designs, the primary coolant is high-purity water, kept under high pressure so it cannot boil.
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
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 water-water energetic reactor (WWER), [1] or VVER (from Russian: водо-водяной энергетический реактор; transliterates as vodo-vodyanoi enyergeticheskiy reaktor; water-water power reactor) is a series of pressurized water reactor designs originally developed in the Soviet Union, and now Russia, by OKB Gidropress. [2]
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 ...
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.
The time required for the molten metal of the core to breach the primary pressure boundary (in light water reactors this is the pressure vessel; in CANDU and RBMK reactors this is the array of pressurized fuel channels; in PHWR reactors like Atucha I, it will be a double barrier of channels and the pressure vessel) will depend on temperatures ...