Article | REF: BN3015 V1

Neutronics basics - Reactor physics and calculations

Author: Paul REUSS

Publication date: January 10, 2006

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4. Multi-group theory

To conclude this dossier, here is a brief overview of neutron calculation methods; it is not possible, within the scope of this document, to go into detail; these can be found in references [2] and [3].

4.1 Principle of multigroup theory

To deal with neutron spectrum problems induced by slowing-down and thermalization processes, we are led, in practice, to discretize the variable E (neutron energy) or the equivalent variables v or u. This discretization is the multigroup method: the range covered by the spectrum from E 0 (maximum neutron energy, around 10 MeV) to E N (minimum energy, practically zero) is divided into N intervals by intermediate bounds E ...

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