This paper discusses the generation of temperature majorant cross sections, the type of cross sections required by two separate techniques related to Monte Carlo neutron tracking, namely, the Dopplerbroadening rejection correction (DBRC) and target motion sampling (TMS) temperature treatment methods. In the generation of these cross sections, the theoretically infinite range of thermal motion must be artificially limited by applying some sort of a cutoff condition, which affects both the accuracy and the performance of the calculations. In this paper, a revised approach for limiting thermal motion is first introduced, and then, optimal cutoff conditions are determined for both the traditional majorant, commonly used in DBRC implementations ...
The Monte Carlo method has been widely used as a standard method to perform neutron transport simula...
Neutron transport relevant to inertial confinement fusion always involves extremes, in which the phy...
Thesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
This paper discusses the generation of temperature majorant cross sections, the type of cross sectio...
The target motion sampling (TMS) temperature treatment technique, previously known as “explicit trea...
This article discusses the optimization of the target motion sampling (TMS) temperature treatment me...
Thermal motion of nuclides has a significant effect on the reaction probabilities and scattering kin...
This article discusses the preliminary implementation of the new explicit temperature treatment meth...
Target Motion Sampling (TMS) is a stochastic on-the-fly temperature treatment technique that is bein...
Target Motion Sampling (TMS) is a stochastic on-the-fly temperature treatment technique that is bein...
This paper introduces a new stochastic method for taking the effect of thermal motion into account o...
A new method to obtain Doppler broadened cross sections has been implemented into MCNP, removing the...
With the rapid development of computational power and parallel algorithms, Monte Carlo method has be...
MCS is an advanced Monte Carlo Simulation code being developed by Ulsan National Institute of Scienc...
MCNP has stood so far as one of the main Monte Carlo radiation transport codes. Its use, as any othe...
The Monte Carlo method has been widely used as a standard method to perform neutron transport simula...
Neutron transport relevant to inertial confinement fusion always involves extremes, in which the phy...
Thesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...
This paper discusses the generation of temperature majorant cross sections, the type of cross sectio...
The target motion sampling (TMS) temperature treatment technique, previously known as “explicit trea...
This article discusses the optimization of the target motion sampling (TMS) temperature treatment me...
Thermal motion of nuclides has a significant effect on the reaction probabilities and scattering kin...
This article discusses the preliminary implementation of the new explicit temperature treatment meth...
Target Motion Sampling (TMS) is a stochastic on-the-fly temperature treatment technique that is bein...
Target Motion Sampling (TMS) is a stochastic on-the-fly temperature treatment technique that is bein...
This paper introduces a new stochastic method for taking the effect of thermal motion into account o...
A new method to obtain Doppler broadened cross sections has been implemented into MCNP, removing the...
With the rapid development of computational power and parallel algorithms, Monte Carlo method has be...
MCS is an advanced Monte Carlo Simulation code being developed by Ulsan National Institute of Scienc...
MCNP has stood so far as one of the main Monte Carlo radiation transport codes. Its use, as any othe...
The Monte Carlo method has been widely used as a standard method to perform neutron transport simula...
Neutron transport relevant to inertial confinement fusion always involves extremes, in which the phy...
Thesis: S.B., Massachusetts Institute of Technology, Department of Nuclear Science and Engineering, ...