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This is a thermal-neutron reactor design. Decommissioning costs can be high due to the large volume of the reactor core. Liquid metal fast-breeder reactor (LMFBR) [moderator: none; coolant: liquid metal] Scaled-down model of TOPAZ nuclear reactor This totally unmoderated reactor design produces more fuel than it consumes.
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.
Two of these were constructed at the Tarapur Atomic Power Station. After a redesign to utilise excess thermal margins, the 540 MW PHWR design achieved a 700 MW capacity without many design changes. Almost 100% of the parts of these indigenously designed reactors are manufactured by Indian industry. [3]
Modern nuclear reactor designs have had numerous safety improvements since the first-generation nuclear reactors. A nuclear power plant cannot explode like a nuclear weapon because the fuel for uranium reactors is not enriched enough, and nuclear weapons require precision explosives to force fuel into a small enough volume to become supercritical.
Nuclear reactor design, which has evolved from the Generation I, proof-of concept, reactors of the 1950s and 1960s, [14] to Generation II, Generation III, and Generation IV concepts; Thermal hydraulics and heat transfer. In a typical nuclear power plant, heat generates steam that drives a steam turbine and a generator that produces electricity
The GFR base design is a fast reactor, but in other ways similar to a high temperature gas-cooled reactor. It differs from the HTGR design in that the core has a higher fissile fuel content as well as a non-fissile, fertile, breeding component. There is no neutron moderator, as the chain reaction is sustained by fast neutrons. Due to the higher ...
When the reactor is prompt critical, the time to double the power is of the order of 10 microseconds. The duration necessary for temperature to follow the power level depends on the design of the reactor core. Typically, the coolant temperature lags behind the power by 3 to 5 seconds in a conventional LWR. In the SL-1 design, it was about 6 ...
The safety systems of the KLT-40S are designed according to the reactor design itself, physical successive systems of protection and containment, self-activating active and passive safety systems, self-diagnostic automatic systems, reliable diagnostics relating to equipment and systems status, and provisioned methods regarding accident control.