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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 ...
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.
A pressurized water reactor (PWR) is a type of light-water nuclear reactor. PWRs constitute the large majority of the world's nuclear power plants (with notable exceptions being the UK, Japan, India and Canada).
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 ...
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.
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 ...
The CPR-1000, or CPR1000 (Chinese PWR) is a Generation II+ pressurized water reactor, based on the French 900 MWe three cooling loop design (M310) imported in the 1980s, improved to have a slightly increased net power output of 1,000 MWe (1080 MWe gross) and a 60-year design life.