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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 ...
Primary NaK Coolant Loop Primärkühlmittelkreislauf, mit NaK Kühlmittel 5 Secondary NaK Coolant Loop Sekundärkühlmittelkreislauf, mit NaK Kühlmittel 6 Secondary NaK Circulator Sekundärkühlmittelpumpe 7 Secondary Heat exhanger: Sekundärwärmeübertrager: 8 Primary Heat Exchanger Primärwärmeübertrager: 9 Primary NaK Circulator
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]
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.
The pool-type reactor design of the EBR-II provides passive safety: the reactor core, its fuel handling equipment, and many other systems of the reactor are submerged under molten sodium. By providing a fluid which readily conducts heat from the fuel to the coolant, and which operates at relatively low temperatures, the EBR-II takes maximum ...
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.
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)
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).