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In nuclear physics, the concept of a neutron cross section is used to express the likelihood of interaction between an incident neutron and a target nucleus. The neutron cross section σ can be defined as the area in cm 2 for which the number of neutron-nuclei reactions taking place is equal to the product of the number of incident neutrons that would pass through the area and the number of ...
The predecessor group to the NNDC was founded in 1951 when a group known as the Brookhaven Neutron Cross Section Compilation Group was formed at the Brookhaven National Laboratory. In 1955 this group published the reference book "BNL-325," which had to do with the cross-sections of neutrons. After being renamed the Sigma Center, the group was ...
The absorption neutron cross section of an isotope of a chemical element is the effective cross-sectional area that an atom of that isotope presents to absorption and is a measure of the probability of neutron capture. It is usually measured in barns. Absorption cross section is often highly dependent on neutron energy. In general, the ...
The cross section obtained in this way is called the total cross section and is usually denoted by a σ or σ T. Typical nuclear radii are of the order 10 −15 m. Assuming spherical shape, we therefore expect the cross sections for nuclear reactions to be of the order of π r 2 {\displaystyle \pi r^{2}} or 10 −28 m 2 (i.e., 1 barn).
Point-wise cross section data are typically used, although group-wise data also are available. For neutrons, all reactions given in a particular cross-section evaluation (such as ENDF/B-VI) are accounted for. Thermal neutrons are described by both the free gas and S(α,β) models.
A thermal neutron is a free neutron with a kinetic energy of about 0.025 eV (about 4.0×10 −21 J or 2.4 MJ/kg, hence a speed of 2.19 km/s), which is the energy corresponding to the most probable speed at a temperature of 290 K (17 °C or 62 °F), the mode of the Maxwell–Boltzmann distribution for this temperature, E peak = k T.
Reaction products originating at distances further from the film/semiconductor interface can not reach the semiconductor surface, and consequently will not contribute to neutron detection. Devices coated with natural Gd have also been explored, mainly because of its large thermal neutron microscopic cross section of 49,000 barns.
The chance is dependent on the nuclide as well as neutron energy. For low and medium-energy neutrons, the neutron capture cross sections for fission (σ F), the cross section for neutron capture with emission of a gamma ray (σ γ), and the percentage of non-fissions are in the table at right. Fertile nuclides in nuclear fuels include: