Liquid metal cooled reactor

Liquid metal cooled reactor

A Liquid metal cooled nuclear reactor, liquid metal fast reactor or LMFR is an advanced type of nuclear reactor where the primary coolant is a liquid metal. Liquid metal cooled reactors were first adapted for nuclear submarine use but have also been extensively studied for power generation applications. They have safety advantages because the reactor doesn't need to be kept under pressure, and they allow a much higher power density than traditional coolants. Disadvantages include difficulties associated with inspection and repair of a reactor immersed in opaque molten metal, and depending on the choice of metal, corrosion and/or production of radioactive activation products may be an issue.

The reactors are used in nuclear power plants to produce nuclear power from nuclear fuel.

Design

In practice, all liquid metal cooled reactors are fast neutron reactors, and to date most fast neutron reactors have been liquid metal cooled fast breeder reactors (LMFBRs), or naval propulsion units. The liquid metals used typically need good heat transfer characteristics. Fast neutron reactor cores tend to generate a lot of heat in a small space when compared to reactors of other classes. A low neutron absorption is desirable in any reactor coolant, but especially important for a fast reactor, as the good neutron economy of a fast reactor is one of its main advantages. Since slower neutrons are more easily absorbed, the coolant should ideally have a low moderation of neutrons. It is also important that the coolant does not cause excessive corrosion of the structural materials, and that its melting and boiling points are suitable for the reactor's operating temperature.

Ideally the coolant should never boil as that would make it more likely to leak out of the system, resulting in a loss of coolant accident. Conversely, if the coolant can be prevented from boiling this allows the pressure in the cooling system to remain at neutral levels, and this dramatically reduces the probability of an accident. Some designs immerse the entire reactor and heat exchangers into a pool of coolant, virtually eliminating the risk that cooling will be lost.

Coolant properties

While pressurised water could theoretically be used for a fast reactor, it tends to slow down neutrons and absorb them. This limits the amount of water that can be allowed to flow through the reactor core, and since fast reactors have a high power density most designs use molten metals instead. Water's boiling point is also much lower than most metals demanding that the cooling system be kept at high pressure to effectively cool the core.

Liquid metal coolants

Common liquid metal coolants used include:

* Molten metals:
** Sodium.
** Lead and bismuth alloys.
* Metals that are liquid at room temperature:
** Mercury.
** NaK.

Each of these have advantages and disadvantages. Mercury is liquid at room temperature, but it is highly toxic and produces noxious fumes when heated, and has thus fallen out of favour.

odium and NaK

Sodium and NaK don't corrode steel to any significant degree and are compatible with many nuclear fuels, allowing for a wide choice of structural materials. They do however ignite spontaneously on contact with air and react violently with water, producing hydrogen gas. Neutron activation of sodium also causes these liquids to become intensely radioactive during operation, though the half-life is short hence their radioactivity doesn't pose an additional disposal concern.

Lead

Lead has excellent neutron properties and is a very potent radiation shield against gamma rays. The very high boiling point of lead provides safety advantages as it can efficiently cool the reactor even if it would reach several hundred degrees Celsius above normal operating conditions. However, because lead has a high melting point it is tricky to refuel and service a lead cooled reactor. The melting point can be lowered by alloying the lead with bismuth, but bismuth is highly corrosive to most metals used for structural materials and is transformed into highly radioactive polonium under neutron bombardment.

Propulsion

ubmarines

The Soviet Alfa class submarine uses a lead cooled reactor, and both the Soviet and US navies had earlier constructed prototype attack submarines using LMFR power units.

USS Seawolf (SSN-575) was the second nuclear submarine, and the only U.S. submarine to have a sodium-cooled nuclear power plant. It was commissioned in 1957, but it had leaks in its superheaters, which were bypassed. In order to standardize the reactors in the fleet, the submarine's sodium-cooled reactor was removed starting in 1958 and replaced with a pressurized water reactor.

Nuclear aircraft

Liquid metal cooled reactors were studied by Pratt & Whitney for use in nuclear aircraft as part of the Aircraft Nuclear Propulsion‎ program. [ [http://www.atomicengines.com/ANP_tech.html The Decay of the Atomic Powered Aircraft Program] ]

Power generation

The Sodium Reactor Experiment (SRE) was an experimental sodium-cooled nuclear reactor sited at the North American Aviation's Atomics International Santa Susana Field Laboratory, located in the Simi Hills, in Ventura County, California, northwest of Los Angeles. On July 26, 1959, the SRE suffered the first partial core meltdown in the history of nuclear power, when the reactor experienced a power excursion that caused severe overheating of the reactor core, resulting in the melting of one-third of the nuclear fuel and significant releases of radioactive gases.

Fermi 1 in Monroe County, Michigan was an experimental, liquid sodium-cooled fast breeder reactor that operated from 1963 to 1972. It suffered a partial nuclear meltdown in 1963 and was decommissioned in 1975.

The Soviet BN-600 and BN-350 and U.S. EBR-II nuclear power plants were sodium cooled. EBR-I used a liquid metal alloy, NaK, for cooling. NaK is liquid at room temperature. Liquid metal cooling is also used in most fast neutron reactors including fast breeder reactors.

Many Generation IV reactor studies are liquid metal cooled:
* Sodium-Cooled Fast Reactor (SFR)
* Lead cooled fast reactor

References


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