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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 ...
Use of NaK overcomes this. The Dounreay Fast Reactor is an example. The first nuclear reactor in space, [10] [11] the United States' experimental SNAP-10A satellite, used NaK as coolant. The NaK was circulated through the core and thermoelectric converters by a liquid metal direct current conduction-type pump. [12]
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
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.
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.
Examples include: Early CANDU reactors (later ones use heavy water moderator but light water coolant) DIDO class research reactors; Liquid metal cooled reactor. Since water is a moderator, it cannot be used as a coolant in a fast reactor. Liquid metal coolants have included sodium, NaK, lead, lead-bismuth eutectic, and in early reactors, mercury.
The removal of heat from nuclear reactors is an essential step in the generation of energy from nuclear reactions.In nuclear engineering there are a number of empirical or semi-empirical relations used for quantifying the process of removing heat from a nuclear reactor core so that the reactor operates in the projected temperature interval that depends on the materials used in the construction ...
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).