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Nuclear reactor where the coolant is liquid metal

A liquid metal cooled nuclear reactor, or LMR is a type of nuclear reactor where the primary coolant is a liquid metal. Liquid metal cooled reactors were first adapted for breeder reactor power generation. They have also been used to power nuclear submarines. Due to their high thermal conductivity, metal coolants remove heat effectively, enabling high power density. This makes them attractive in situations where size and weight are at a premium, like on ships and submarines. Most water based reactor designs are highly pressurized to raise the boiling point (thereby improving cooling capabilities), which presents safety and maintenance issues that liquid metal designs lack. Additionally, the high temperature of the liquid metal can be used to drive power conversion cycles with high thermodynamic efficiency. This makes them attractive for improving power output, cost effectiveness, and fuel efficiency in nuclear power plants. Liquid metals, being electrically highly conductive, can be moved by electromagnetic pumps. Disadvantages include difficulties associated with inspection and repair of a reactor immersed in opaque molten metal, and depending on the choice of metal, fire hazard risk (for alkali metals), corrosion and/or production of radioactive activation products may be an issue.

Liquid metal coolant has been applied to both thermal and fast neutron reactors. To date, most fast neutron reactors have been liquid metal cooled and so are called liquid metal cooled fast reactors (LMFRs). When configured as a breeder reactor (e. g. with a breeding blanket), such reactors are called liquid metal fast breeder reactors (LMFBRs).

Suitable liquid metal coolants must have a low neutron capture cross section, must not cause excessive corrosion of the structural materials, and must have melting and boiling points that are suitable for the reactor's operating temperature. Liquid metals generally have high boiling points, reducing the probability that the coolant can boil, which could lead to a loss of coolant accident. Low vapor pressure enables operation at near ambient pressure, further dramatically reducing the probability of an accident. Some designs immerse the entire core and heat exchangers into a pool of coolant, virtually eliminating the risk that inner loop cooling will be lost. +Liquid metal coolantsMetal CoolantMelting pointBoiling pointSodium97.72 °C, (207.9 °F)883 °C, (1621 °F)NaK−11 °C, (12 °F)785 °C, (1445 °F)Mercury−38.83 °C, (−37.89 °F) 356.73 °C (674.11 °F)Lead327.46 °C, (621.43 °F)1749 °C, (3180 °F)Lead bismuth eutectic123.5 °C, (254.3 °F) 1670 °C, (3038 °F)Tin231.9 °C, (449.5 °F) 2602 °C, (4716 °F)

Clementine was the first liquid metal cooled nuclear reactor and used mercury coolant, thought to be the obvious choice since it is liquid at room temperature. However, because of disadvantages including high toxicity, high vapor pressure even at room temperature, low boiling point producing noxious fumes when heated, relatively low thermal conductivity, and a high neutron cross section, it has fallen out of favor.

Sodium and NaK (a eutectic sodium potassium alloy) do not corrode steel to any significant degree and are compatible with many nuclear fuels, allowing for a wide choice of structural materials. 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 used in the Russian BN reactor series and the Chinese CFR series in commercial operation today. Neutron activation of sodium also causes these liquids to become intensely radioactive during operation, though the half life is short and therefore their radioactivity does not pose an additional disposal concern. There are two proposals for a sodium cooled Gen IV LMFR, one based on oxide fuel, the other on the metal fueled integral fast reactor.

Lead has excellent neutron properties (reflection, low absorption) and is a very potent radiation shield against gamma rays. The high boiling point of lead provides safety advantages as it can cool the reactor efficiently even if it reaches several hundred degrees Celsius above normal operating conditions. However, because lead has a high melting point and a high vapor pressure, it is tricky to refuel and service a lead cooled reactor. The melting point can be lowered by alloying the lead with bismuth, but lead bismuth eutectic is highly corrosive to most metals used for structural materials.

Lead bismuth eutectic allows operation at lower temperatures while preventing the freezing of the metal coolant in a lower temperature range (eutectic point: 123.5 °C / 255.3 °F). Beside its highly corrosive character, it can be a useful additional or replacement coolant at nuclear disasters or loss of coolant accidents. Further advantages of tin are the high boiling point and the ability to build a crust even over liquid tin helps to cover poisonous leaks and keeps the coolant in and at the reactor. It has been tested by Ukrainian researchers and was proposed to convert the boiling water reactors at the Fukushima Daiichi nuclear disaster into liquid tin cooled reactors.

The Soviet Soviet submarine K 27 and all seven s used reactors cooled by lead bismuth eutectic and moderated with beryllium as their propulsion plants. (VT 1 reactors in K 27; BM 40A and OK 550 reactors in others). The second nuclear submarine, Seawolf was the only U. S. submarine to have a sodium cooled, beryllium moderated 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, beryllium moderated reactor was removed starting in 1958 and replaced with a pressurized water reactor.

Liquid metal cooled reactors were studied by Pratt & Whitney for use in nuclear aircraft as part of the Aircraft Nuclear Propulsion program.