Resonance absorption calculations in thermal reactors

Rothenstein, W.

doi:10.1016/0149-1970(80)90003-7

Cited by 8 publications

(1 citation statement)

References 35 publications

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“…A reasonable approximation can be made by considering a spectrum of average moderator flux in pin cells close to the boundary. Assuming that the problem consists only of moderator and a single fuel type, and noting that the neutrons energy loss in collisions with the moderator is typically much larger than resonance widths, it is possible to write an expression for the flux in the moderator as a function of energy using the Narrow Resonance Approximation [12]:…”

Section: Resonance Correctionmentioning

confidence: 99%

A hybrid continuous energy and multi-group Monte Carlo method

Kowalski

Shwageraus

2020

Annals of Nuclear Energy

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This paper investigates mixing multi-group (MG) and continuous energy (CE) representation of cross-sections depending on location of a particle in a Monte Carlo neutronic eigenvalue calculations in 1D and 2D PWR test cases with UOX and MOX fuel. Different population normalisation needs to be applied to CE and MG region to account for the difference in criticality between CE and MG representation. This normalisation procedure requires a neutron production rate ratio between CE and MG region to be known a priori. A resonance correction in energy spectrum during transition of a particle between the MG and CE region was developed based on the equivalence resonance treatment theory. With these, it was shown that it is possible to accelerate total calculation time, while introducing only a moderate error below 1% in the fission rate distribution. The magnitude of acceleration is heavily dependent on the relative size of CE and MG zones.

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Section: Resonance Correctionmentioning

confidence: 99%