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NaK was used as the coolant in the first breeder reactor prototype, the Experimental Breeder Reactor-1, in 1951. Sodium and NaK do, however, ignite spontaneously on contact with air and react violently with water, producing hydrogen gas. This was the case at the Monju Nuclear Power Plant in a 1995 accident and fire. Sodium is also the coolant ...
NaK containing 40% to 90% potassium by mass is liquid at room temperature.The eutectic mixture consists of 77% potassium and 23% sodium by mass (NaK-77), and it is a liquid from −12.6 to 785 °C (9.3 to 1,445.0 °F), and has a density of 0.866 g/cm 3 at 21 °C (70 °F) and 0.855 g/cm 3 at 100 °C (212 °F), making it less dense than water. [3]
Primary NaK Coolant Loop ... distribute and/or modify this document under the terms of the GNU Free Documentation ... Dounreay Fast Reactor (DFR), a liquid-w ...
A nuclear reactor coolant is a coolant in a nuclear reactor used to remove heat from the nuclear reactor core and transfer it to electrical generators and the environment. Frequently, a chain of two coolant loops are used because the primary coolant loop takes on short-term radioactivity from the reactor.
Schematic diagram showing the difference between the Pool and Loop designs of a liquid metal fast breeder reactor. The two main design approaches to sodium-cooled reactors are pool type and loop type. In the pool type, the primary coolant is contained in the main reactor vessel, which therefore includes the reactor core and a heat exchanger.
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
On the other hand, if a reactor is designed to operate with no voids at all, a large negative void coefficient may serve as a safety system. A loss of coolant in such a reactor decreases the thermal output, but of course heat that is generated is no longer removed, so the temperature could rise (if all other safety systems simultaneously failed).
The aim of the template is to show the characteristics of an reactor design (e.g. RBMK) or individual experimental or prototype reactors (e.g. Chicago Pile-1 or Superphénix), but not for individual power plants (e.g. not Chernobyl Nuclear Power Plant)