- Neutron temperature
The neutron detection temperature, also called the neutron energy, indicates a free neutron's kinetic energy, usually given in electron volts. The term temperature is used, since hot, thermal and cold neutrons are moderated in a medium with a certain temperature. The neutron energy distribution is then adopted to the Maxwellian distribution known for thermal motion. Qualitatively, the higher the temperature, the higher the kinetic energy is of the free neutron. Kinetic energy, speed and wavelength of the neutron are related through the De Broglie relation.
Neutron energy distribution ranges
Moderated and other, non-thermal neutron energy distributions or ranges are listed in the table below:
- Fast neutrons have an energy greater than 1 eV, 0.1 MeV or approximately 1 MeV, depending on the definition.
- Slow neutrons have an energy less than or equal 0.4 eV.
- Epithermal neutrons have an energy from 1 eV to 10 keV.
- Hot neutrons have an energy of about 0.2 eV.
- Thermal neutrons have an energy of about 0.025 eV.
- Cold neutrons have an energy from 5x10−5 eV to 0.025 eV.
- Very cold neutrons have an energy from 3x10−7 eV to 5x10−5 eV.
- Ultra cold neutrons have an energy less than 3x10−7 eV.
- Continuum region neutrons have an energy from 0.01 MeV to 25 MeV.
- Resonance region neutrons have an energy from 1 eV to 0.01 MeV.
- Low energy region neutrons have an energy less than 1 eV.
A fast neutron is a free neutron with a kinetic energy level close to 1 MeV (100 TJ/kg), hence a speed of 14,000 km/s. They are named fast neutrons to distinguish them from lower-energy thermal neutrons, and high-energy neutrons produced in cosmic showers or accelerators. Fast neutrons are produced by nuclear processes such as nuclear fission.
Neutrons from fusion reactions are usually considerably more energetic than 1 MeV; the extreme case is deuterium-tritium fusion which produces 14.1 MeV neutrons (1400 TJ/kg, moving at 52,000 km/s, 17.3% of the speed of light) that can easily fission uranium-238 and other non-fissile actinides.
Fast neutrons can be made into thermal neutrons via a process called moderation. This is done with a neutron moderator. In reactors, typically heavy water, light water, or graphite are used to moderate neutrons.
A thermal neutron is a free neutron with a kinetic energy of about 0.025 eV (approx. 4.0×10−21 J; 2.4 MJ/kg, hence a speed of 2.2 km/s) which is the energy corresponding to the most probable velocity at a temperature of 290 K (17°C or 62°F), the mode of the Maxwell–Boltzmann distribution for this temperature.
Thermal neutrons have a different and often much larger effective neutron absorption cross-section for a given nuclide than fast neutrons, and can therefore often be absorbed more easily by an atomic nucleus, creating a heavier - and often unstable - isotope of the chemical element as a result (neutron activation).
Fast reactor and thermal reactor compared
Most fission reactors are thermal reactors that use a neutron moderator to slow down, or thermalize the neutrons produced by nuclear fission. Moderation substantially increases the fission cross section for fissile nuclei such as uranium-235 or plutonium-239. In addition, uranium-238 also has a much lower capture cross section for thermal neutrons, allowing more neutrons to cause fission of fissile nuclei and continue the chain reaction, rather than being captured by 238U. The combination of these effects allows light water reactors to use low-enriched uranium. Heavy water reactors and graphite-moderated reactors can even use natural uranium as these moderators have much lower neutron capture cross sections than light water.
An increase in fuel temperature also raises U-238's thermal neutron absorption by Doppler broadening, providing negative feedback to help control the reactor. Also, when the moderator is also a circulating coolant (light water or heavy water), boiling of the coolant will reduce the moderator density and provide negative feedback (a negative void coefficient).
Intermediate-energy neutrons have poorer fission/capture ratios than either fast or thermal neutrons for most fuels. An exception is the uranium-233 of the thorium cycle which has a good fission/capture ratio at all neutron energies.
Fast reactors use unmoderated fast neutrons to sustain the reaction and require the fuel to contain a higher concentration of fissile material relative to fertile material U-238. However, fast neutrons have a better fission/capture ratio for many nuclides, and each fast fission releases a larger number of neutrons, so a fast breeder reactor can potentially "breed" more fissile fuel than it consumes.
Fast reactor control cannot depend solely on Doppler broadening or on negative void coefficient from a moderator. However, thermal expansion of the fuel itself can provide quick negative feedback. Perennially expected to be the wave of the future, fast reactor development has been nearly dormant with only a handful of reactors built in the decades since the Chernobyl accident (and because of low prices in the uranium market)-- although there is now a revival with several Asian countries planning to complete larger prototype fast reactors in the next few years.
Wikimedia Foundation. 2010.
Look at other dictionaries:
neutron temperature — neutronų temperatūra statusas T sritis fizika atitikmenys: angl. neutron temperature vok. Neutronentemperatur, f rus. температура нейтронов, f pranc. température neutronique, f … Fizikos terminų žodynas
neutron temperature — /njutrɒn ˈtɛmprətʃə/ (say nyoohtron tempruhchuh) noun the energy of neutrons, in thermal equilibrium with their surroundings, expressed as a temperature on the assumption that they behave as a monatomic gas … Australian English dictionary
Neutron — This article is about the subatomic particle. For other uses, see Neutron (disambiguation). Neutron The quark structure of the neutron. (The color assignment of individual quarks is not important, only that all three colors are present.)… … Wikipedia
Neutron cross section — Science with Neutrons Foundations Neutron temperature Flux · Radiation … Wikipedia
Neutron moderator — Currently operating nuclear power reactors by moderator Moderator Reactors Design Country none (fast) 1 BN 600 Russia (1) graphite 29 AGR, Magnox, RBMK United Kingdom (18), Russia (11) heavy water 29 CANDU … Wikipedia
Neutron scattering — Science with Neutrons Foundations Neutron temperature Flux · Radiation … Wikipedia
Neutron activation analysis — Science with Neutrons Foundations Neutron temperature Flux · Radiation … Wikipedia
Neutron source — Science with Neutrons Foundations Neutron temperature Flux · Radiation … Wikipedia
Neutron diffraction — Science with Neutrons Foundations Neutron temperature Flux · Radiation … Wikipedia
Neutron capture — Science with Neutrons Foundations Neutron temperature Flux · Radiation … Wikipedia