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English: Generation II nuclear reactor vessel sizes of similar power output: PWR: typical Westinghouse 4 loop reactor pressure vessel (3411MWt, 1125MWe). CANDU: Darlington reactor calandria (2657MWt, 935MWe). BWR-4 reactor pressure vessel (3293MWt, 1098MWe). RBMK-1000 reactor steel vessel, biological shields, and water tank (3200MWt, 1000MWe).
English: Schematic diagram of an Advanced Gas-cooled Reactor type nuclear reactor 1. Charge tubes 2. Control rods 3. Graphite moderator 4. Fuel assemblies 5. Concrete pressure vessel and radiation shielding 6. Gas circulator 7. Water 8. Water circulator 9. Heat exchanger 10. Steam
English: Nuclear reactor: pressurized water type. Water is heated through the splitting of uranium atoms in the reactor core. The water, held under high pressure to keep it from boiling, produces steam by transferring heat to a secondary source of water. The steam is used to generate electricity.
A reactor vessel head for a pressurized water reactor. This structure is attached to the top of the reactor vessel body. It contains penetrations to allow the control rod driving mechanism to attach to the control rods in the fuel assembly. The coolant level measurement probe also enters the vessel through the reactor vessel head.
For power use, the fuel canisters were left in the reactor as long as possible, while for plutonium production they were removed earlier. The complicated refuelling equipment proved to be less reliable than the reactor systems, and perhaps not advantageous overall. [6] The entire reactor assembly was placed in a large pressure vessel.
A BWR's containment consists of a drywell, where the reactor and associated cooling equipment is located, and a wetwell. The drywell is much smaller than a PWR containment and plays a larger role. During the theoretical leakage design basis accident, the reactor coolant flashes to steam in the drywell, pressurizing it rapidly.
The advanced gas-cooled reactor (AGR) is a type of nuclear reactor designed and operated in the United Kingdom. These are the second generation of British gas-cooled reactors , using graphite as the neutron moderator and carbon dioxide as coolant.
The VVER-TOI reactor pressure vessel has fewer welds than the VVER-1200, all out of the central area, and a more symmetric arrangement of coolant nozzles. This gives the potential for two 20 year life extensions, which could give a 100 year life.