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  2. Neutron temperature - Wikipedia

    en.wikipedia.org/wiki/Neutron_temperature

    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.

  3. Fissile material - Wikipedia

    en.wikipedia.org/wiki/Fissile_material

    Fissile nuclides do not have a 100% chance of undergoing fission on absorption of a neutron. 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 ...

  4. Valley of stability - Wikipedia

    en.wikipedia.org/wiki/Valley_of_stability

    The chart of those nuclides is also known as a Segrè chart, after the physicist Emilio Segrè. [3] The Segrè chart may be considered a map of the nuclear valley. The region of proton and neutron combinations outside of the valley of stability is referred to as the sea of instability. [4] [5]

  5. Uranium-235 - Wikipedia

    en.wikipedia.org/wiki/Uranium-235

    Uranium-235 (235 U or U-235) is an isotope of uranium making up about 0.72% of natural uranium.Unlike the predominant isotope uranium-238, it is fissile, i.e., it can sustain a nuclear chain reaction.

  6. Critical mass - Wikipedia

    en.wikipedia.org/wiki/Critical_mass

    In nuclear engineering, a critical mass is the smallest amount of fissile material needed for a sustained nuclear chain reaction. The critical mass of a fissionable material depends upon its nuclear properties (specifically, its nuclear fission cross-section), density, shape, enrichment, purity, temperature, and

  7. Nuclear fuel - Wikipedia

    en.wikipedia.org/wiki/Nuclear_fuel

    While exposed to the neutron flux during normal operation in the core environment, a small percentage of the 238 U in the fuel absorbs excess neutrons and is transmuted into 239 U. 239 U rapidly decays into 239 Np which in turn rapidly decays into 239 Pu. The small percentage of 239 Pu has a higher neutron cross section than 235 U.

  8. Neutron cross section - Wikipedia

    en.wikipedia.org/wiki/Neutron_cross_section

    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 ...

  9. Neutron - Wikipedia

    en.wikipedia.org/wiki/Neutron

    Toggle Neutron temperature subsection. 13.1 Thermal neutrons. 13.2 Cold neutrons. 13.3 Ultracold neutrons. ... 12–13 For a given mass of fissile material, ...