Nuclear reactor coolant

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Nuclear reactor coolants
Coolant Melting point Boiling point
Heavy water at 155 bar 345 °C
NaK eutectic -11 °C 785 °C
Sodium 97.72 °C 883 °C
FLiNaK 454 °C 1570 °C
FLiBe 459 °C 1430 °C
Lead 327.46 °C 1749 °C
Lead-bismuth eutectic 123.5 °C 1670 °C

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.

Water[edit]

Almost all currently operating nuclear power plants are light water reactors using ordinary water under high pressure as coolant and neutron moderator. About 1/3 are boiling water reactors where the primary coolant undergoes phase transition to steam inside the reactor. About 2/3 are pressurized water reactors at even higher pressure. Current reactors stay under the critical point at around 374 °C and 218 bar where the distinction between liquid and gas disappears, which limits thermal efficiency, but the proposed supercritical water reactor would operate above this point.

Heavy water reactors (CANDU) use deuterium oxide which has identical properties to ordinary water but much lower neutron capture, allowing more thorough moderation.

Disadvantages[edit]

Tritium leak[edit]

As the hydrogen atoms in water coolants are bombarded with neutrons, some absorb a neutron to become deuterium, and then some become radioactive tritium. Water contaminated with tritium sometimes leaks to groundwater by accident or by official approval[1]

Hydrogen explosion during power outage[edit]

The fuel rods create high temperatures which boil water then turn water to steam. During a disaster, when a power outage happens and diesel power generators which provide emergency power to the water pump are damaged by a tsunami or an earthquake, if no fresh water is being pumped to cool the fuel rods then the fuel rods continue to heat up. Once the fuel rods reach more than 1200 degrees Celsius, the zirconium tubes that contain the nuclear fuel will interact with the steam and split the hydrogen from the water. That hydrogen can then be released from the reactor core and containment vessel. If that hydrogen accumulates in sufficient quantities-concentrations of 4 percent or more in the air, then that hydrogen can explode, as has apparently occurred at Fukushima Daiichi reactors No. 1, 3, 4 but reactor No. 2 opened its vent to let out radioactive hydrogen gas, decreasing the pressure of the hydrogen, but it contaminated the environment, so reactor No. 2 did not explode[2]

Borated water[edit]

Borated water is used as a coolant during normal operation of pressurized water reactors (PWRs) as well as in Emergency Core Cooling Systems (ECCS) of both PWRs and boiling water reactors (BWRs).[3][4][5]

Advantages[edit]

Boron, often in the form of boric acid or sodium borate, is combined with water — a cheap and plentiful resource — where it acts as a coolant to remove heat from the reactor core and transfers the heat to a secondary circuit.[6] Part of the secondary circuit is the steam generator that is used to turn turbines and generate electricity. Borated water also provides the additional benefits of acting as a neutron poison due to its large neutron absorption cross-section, where it absorbs excess neutrons to help control the fission rate of the reactor. Thus, the reactivity of the nuclear reactor can be easily adjusted by changing the boron concentration in the coolant. That is, when the boron concentration is increased (boration) by dissolving more boric acid into the coolant, the reactivity of the reactor is decreased. Conversely, when the boron concentration is decreased (dilution) by adding more water, the reactivity of the reactor is increased.[7]

Disadvantages[edit]

Approximately 90% of the tritium in PWR coolants is produced by reactions of boron-10 with neutrons. Since tritium itself is a radioactive isotope of hydrogen, the coolant becomes contaminated with radioactive isotopes and must be kept from leaking into the environment. Additionally, this effect must be taken into account for longer cycles of nuclear reactor operation and thus requires higher initial concentration of boron in the coolant.[7]

Molten metal[edit]

Fast reactors have a high power density and do not need neutron moderation. Most have been liquid metal cooled reactors using molten sodium. Lead, lead-bismuth eutectic, and other metals have also been proposed and occasionally used. Mercury was used in the first fast reactor.

Molten salt[edit]

Molten salts share with metals the advantage of low vapor pressure even at high temperatures, and are less chemically reactive than sodium. Salts containing light elements like FLiBe can also provide moderation. In the Molten-Salt Reactor Experiment it even served as a solvent carrying the nuclear fuel.

Gas[edit]

Gases have also been used as coolant. Helium is extremely inert both chemically and with respect to nuclear reactions but has a low heat capacity,

Hydrocarbons[edit]

Organically moderated and cooled reactors was an early power reactor concept studied,in which hydrocarbon is used as nuclear coolant. They were not successful.

References[edit]

  1. ^ "as the result of routine, approved releases;from google (why tritium leak) result 2".
  2. ^ "Partial Meltdowns Led to Hydrogen Explosions at Fukushima Nuclear Power Plant;from google (fukushima hydrogen explosion) result 1".
  3. ^ "Pressurized Water Reactor Systems" (PDF). USNRC Technical Training Center. Retrieved March 12, 2019.
  4. ^ Aaltonen1, Hanninen2, P.1, H.2. "Water Chemistry and Behavior of Materials in PWRs and BWRs" (PDF). VTT Manufacturing Technology. Retrieved March 12, 2019.
  5. ^ Buongiorno, Jacopo. "Nuclear Safety" (PDF). MIT OpenCourseWare. Retrieved March 12, 2019.
  6. ^ "Borated Water" (PDF). Columbus Chemical Industries. Retrieved March 12, 2019.
  7. ^ a b Monterrosa, Anthony (May 5, 2012). "Boron Use and Control in PWRs and FHRs" (PDF). Department of Nuclear Engineering, University of California, Berkeley. Retrieved March 12, 2019.

External links[edit]