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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 ...
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.
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
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.
A positive void coefficient means that the reactivity increases as the void content inside the reactor increases due to increased boiling or loss of coolant; for example, if the coolant acts predominantly as neutron absorber. This positive void coefficient causes a positive feedback loop, starting with the first occurrence of steam bubbles ...
DFR was a loop-type FBR cooled by primary and secondary NaK circuits, with 24 primary coolant loops. The reactor core was initially fuelled with uranium metal fuel stabilised with molybdenum and clad in niobium. The core was later used to test oxide fuels for PFR and provide experimental space to support overseas fast reactor fuel and materials ...