In this work, we present the derivation and investigation of a new Doppler broadening rejection sampling approach for the exact treatment of resonance elastic scattering in Monte Carlo neutron transport codes. Implemented in OpenMC, this method correctly accounts for the energy dependence of cross sections when treating the thermal motion of target nuclei in elastic scattering events. The method is verified against both stochastic and deterministic reference results in the literature for ²³⁸U resonance scattering. Upscatter percentages and mean scattered energies calculated with the method are shown to agree well with the reference scattering kernel results. Additionally, pin cell and full core k[subscript eff] results calculated with this ...
Distributions of inelastically scattered neutrons can be quantum dynamically described by a scatteri...
This document presents the statistical description of neutron cross sections in the unresolved reson...
International audienceCross sections are crucial nuclear data that describe the probability for a pa...
Thesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
Current Monte Carlo codes use one of three models: (1) the asymptotic scattering model, (2) the free...
The effects of accurate modeling of neutron scattering in 238U resonances are analyzed for typical l...
Experimental measurements of elastic neutron scattering from 238U resonances were used to benchmark ...
Based on the resonance integral (RI) tables produced by the NJOY program, the conventional subgroup ...
AbstractBased on the resonance integral (RI) tables produced by the NJOY program, the conventional s...
Recent works have pointed out some relevant shortcomings of the so called ‘Sampling of the Velocity ...
In this work we present a scheme for computing temperature-dependent unresolved resonance region cro...
In this work we describe the development and application of computational methods for processing neu...
The theory, implementation, and testing of a method for on-the-fly unresolved resonance region cross...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
Distributions of inelastically scattered neutrons can be quantum dynamically described by a scatteri...
This document presents the statistical description of neutron cross sections in the unresolved reson...
International audienceCross sections are crucial nuclear data that describe the probability for a pa...
Thesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
Current Monte Carlo codes use one of three models: (1) the asymptotic scattering model, (2) the free...
The effects of accurate modeling of neutron scattering in 238U resonances are analyzed for typical l...
Experimental measurements of elastic neutron scattering from 238U resonances were used to benchmark ...
Based on the resonance integral (RI) tables produced by the NJOY program, the conventional subgroup ...
AbstractBased on the resonance integral (RI) tables produced by the NJOY program, the conventional s...
Recent works have pointed out some relevant shortcomings of the so called ‘Sampling of the Velocity ...
In this work we present a scheme for computing temperature-dependent unresolved resonance region cro...
In this work we describe the development and application of computational methods for processing neu...
The theory, implementation, and testing of a method for on-the-fly unresolved resonance region cross...
Thesis: S.M., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
Thesis: Ph. D., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering...
Distributions of inelastically scattered neutrons can be quantum dynamically described by a scatteri...
This document presents the statistical description of neutron cross sections in the unresolved reson...
International audienceCross sections are crucial nuclear data that describe the probability for a pa...