Abstract
The common approach of representing energy dependence of neutron–nucleus interactions consists of discretizing the energy dependence in a number of energy groups. During the fission reactions neutrons are emitted with an average energy of approximately 2 MeV. Neutron numbers are negligibly small above 10–15 MeV, making the maximum energy of interest in most nuclear fission reactors to be of about 15 MeV. Neutrons are then slowed down to much lower energies by collisions with the reactor components.
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- 1.
Multilevel theory can also be used, and this method is available in addition to the single-level formulation in the legacy MINX code and in the general purpose NJOY code. Single-level theory is usually adequate, however.
- 2.
The Maxwellian distribution holds strictly only for a gas, whereas the resonance absorber is a solid. Above a temperature referred to as the Debye temperature (based on Debye’s model for solids) this distribution is satisfactory for solids. The Debye temperature for most solids is of the order of 300 K: hence, the distribution holds for the entire range of fast reactor temperatures.
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Tsvetkov, P., Waltar, A. (2012). Nuclear Data and Cross Section Processing. In: Waltar, A., Todd, D., Tsvetkov, P. (eds) Fast Spectrum Reactors. Springer, Boston, MA. https://doi.org/10.1007/978-1-4419-9572-8_5
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