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When a uranium nucleus fissions into two daughter nuclei fragments, about 0.1 percent of the mass of the uranium nucleus [15] appears as the fission energy of ~200 MeV. For uranium-235 (total mean fission energy 202.79 MeV [16]), typically ~169 MeV appears as the kinetic energy of the daughter nuclei, which fly apart at about 3% of the speed of ...
Other fission products, such as xenon-135 and samarium-149, have a high neutron absorption cross section. Since a nuclear reactor must balance neutron production and absorption rates, fission products that absorb neutrons tend to "poison" or shut the reactor down; this is controlled with burnable poisons and control rods.
Spontaneous fission (SF) is a form of radioactive decay in which a heavy atomic nucleus splits into two or more lighter nuclei. In contrast to induced fission , there is no inciting particle to trigger the decay; it is a purely probabilistic process.
Fission product yields by mass for thermal neutron fission of U-235 and Pu-239 (the two typical of current nuclear power reactors) and U-233 (used in the thorium cycle). This page discusses each of the main elements in the mixture of fission products produced by nuclear fission of the common nuclear fuels uranium and plutonium.
Nuclear fission splits a heavy nucleus such as uranium or plutonium into two lighter nuclei, which are called fission products. Yield refers to the fraction of a fission product produced per fission. Yield can be broken down by: Individual isotope; Chemical element spanning several isotopes of different mass number but same atomic number.
Uranium-235 has a half-life of 703.8 million years. It was discovered in 1935 by Arthur Jeffrey Dempster. Its fission cross section for slow thermal neutrons is about 584.3 ± 1 barns. [1] For fast neutrons it is on the order of 1 barn. [2] Most neutron absorptions induce fission, though a minority (about 15%) result in the formation of uranium ...
Uranium-233 (233 U or U-233) is a fissile isotope of uranium that is bred from thorium-232 as part of the thorium fuel cycle. Uranium-233 was investigated for use in nuclear weapons and as a reactor fuel. [2] It has been used successfully in experimental nuclear reactors and has been proposed for much wider use as a nuclear fuel.
In nuclear power technology, burnup is a measure of how much energy is extracted from a given amount of nuclear fuel. [1] It may be measured as the fraction of fuel atoms that underwent fission in %FIMA (fissions per initial heavy metal atom) [2] or %FIFA (fissions per initial fissile atom) [3] as well as the actual energy released per mass of initial fuel in gigawatt-days/metric ton of heavy ...