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Thermal-neutron reactor

From Wikipedia, the free encyclopedia
(Redirected fromThermal reactor)
Nuclear reactor, uses moderated neutrons
Main article:Nuclear reactor

Athermal-neutron reactor is anuclear reactor that uses slow orthermal neutrons. ("Thermal" does not mean hot in an absolute sense, but means inthermal equilibrium with the medium it is interacting with, the reactor's fuel, moderator and structure, which is much lower energy than thefast neutrons initially produced by fission.)

Mostnuclear power plant reactors are thermal reactors and use aneutron moderator to slowneutrons until they approach the averagekinetic energy of the surrounding particles, that is, to reduce the speed of the neutrons to low-velocity, thermal neutrons. Neutrons are uncharged, this allows them to penetrate deep in the target and close to the nuclei, thus scattering neutrons by nuclear forces, some nuclides are scattered large.[1]

Thenuclear cross section ofuranium-235 for slow thermal neutrons is about 1000barns, while for fast neutrons it is in the order of 1 barn.[2] Therefore, thermal neutrons are more likely to cause uranium-235 tonuclear fission than to be captured byuranium-238. If at least one neutron from the U-235 fission strikes another nucleus and causes it to fission, then thechain reaction will continue. If the reaction will sustain itself, it is said to becritical, and the mass of U-235 required to produce the critical condition is said to be acritical mass.

Thermal reactors consist of the following:

Types of thermal-neutron reactor

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Light-Water Reactor, LWR

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These paragraphs are an excerpt fromLight-water reactor.[edit]

Thelight-water reactor (LWR) is a type of thermal-neutron reactor that uses normal water, as opposed to , as both its coolant and ; furthermore a solid form of fissile elements is used as fuel. Thermal-neutron reactors are the most common type of , and light-water reactors are the most common type of thermal-neutron reactor.

There are three varieties of light-water reactors: the (PWR), the (BWR), and (most designs of) the (SCWR).

Heavy Water Reactor, HWR

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This paragraph is an excerpt fromHeavy-water reactor.[edit]
Aheavy water reactor (HWR) is a type of which uses (D2O, oxide) as a . It may also use this as the coolant, in the case of . Due to heavy water's low neutron absorption cross section, HWRs can operate with fuel.

Gas-Cooled Reactor, GCR

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This paragraph is an excerpt fromGas-cooled reactor.[edit]
Agas-cooled reactor (GCR) is a that uses as a and a gas ( or in extant designs) as . Although there are many other types of reactor cooled by gas, the termsGCR and to a lesser extentgas cooled reactor are particularly used to refer to this type of reactor.

Examples by generation

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Generation I (1950s–1960s)

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These were early prototypes and demonstration reactors.

Generation II (1970s–1990s)

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Commercial reactors with standardized designs and improved safety.

All of these are thermal reactors using moderators like water or graphite.

Generation III / III+ (1990s–present)

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Enhanced safety, longer lifespans, and passive safety systems.

  • AP1000 (USA): A Gen III+ PWR with passive cooling.
  • EPR (European Pressurized Reactor): High-output PWR used in France and Finland.
  • VVER-1200 (Russia): Modernized version of Soviet PWRs.
  • CANDU 6 Enhanced: Updated heavy water reactor with improved safety.

See also

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References

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  1. ^Squires, G. L. (2012-03-29).Introduction to the Theory of Thermal Neutron Scattering. Cambridge University Press.ISBN 978-1-107-64406-9.
  2. ^"Some Physics of Uranium". Archived fromthe original on March 3, 2008. Retrieved2009-01-18.

Further reading

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