[HTML][HTML] CAD-based Monte Carlo program for integrated simulation of nuclear system SuperMC

Y Wu, J Song, H Zheng, G Sun, L Hao, P Long… - Annals of Nuclear …, 2015 - Elsevier
Monte Carlo (MC) method has distinct advantages to simulate complicated nuclear systems
and is envisioned as a routine method for nuclear design and analysis in the future. High …

Single-step Monte Carlo criticality algorithm

Q Pan, N An, T Zhang, X Liu, Y Cai, L Wang… - Computer Physics …, 2022 - Elsevier
A single-step Monte Carlo criticality algorithm is proposed to improve the efficiency of Monte
Carlo criticality calculation. This algorithm adopts the strategy of increasing neutron …

Asymptotic hydrogen redistribution analysis in yttrium-hydride-moderated heat-pipe-cooled microreactors using DireWolf

S Terlizzi, V Labouré - Annals of Nuclear Energy, 2023 - Elsevier
Yttrium hydride (YH x) is one of the materials being considered for moderating thermal and
epithermal nuclear microreactors. One potential issue with YH x use is that the hydrogen …

Application of artificial neural network for assembly homogenized equivalence parameter generation

S Dzianisau, D Lee - Progress in Nuclear Energy, 2024 - Elsevier
The development of a new reactor core and optimizations for fuel assembly (FA) structures
necessitates the generation of homogenized equivalence parameters, including …

Monte Carlo and thermal hydraulic coupling using low-order nonlinear diffusion acceleration

BR Herman - 2014 - dspace.mit.edu
Monte Carlo (MC) methods for reactor analysis are most often employed as a benchmark
tool for other transport and diffusion methods. In this work, we identify and resolve a few of …

[HTML][HTML] Domain decomposition for GPU-Based continuous energy Monte Carlo power reactor calculation

N Choi, HG Joo - Nuclear Engineering and Technology, 2020 - Elsevier
A domain decomposition (DD) scheme for GPU-based Monte Carlo (MC) calculation which
is essential for whole-core depletion is introduced within the framework of the modified …

A multilevel in space and energy solver for 3-D multigroup diffusion and coarse-mesh finite difference eigenvalue problems

BC Yee, B Kochunas, EW Larsen - Nuclear Science and …, 2019 - Taylor & Francis
Abstract The Multilevel in Space and Energy Diffusion (MSED) method accelerates the
iterative convergence of multigroup diffusion eigenvalue problems by performing work on …

Analysis of correlations and their impact on convergence rates in Monte Carlo eigenvalue simulations

J Miao, B Forget, K Smith - Annals of Nuclear Energy, 2016 - Elsevier
This paper provides an analysis of the generation-to-generation correlations as observed
when solving full core eigenvalue problems on PWR systems. Many studies have in the past …

A consistent CMFD formulation for the acceleration of neutron transport calculations based on the finite element method

YS Jung, WS Yang - Nuclear Science and Engineering, 2017 - Taylor & Francis
This paper presents the method and performance of a coarse-mesh finite difference (CMFD)
scheme for accelerating neutron transport calculations based on the finite element method …

Optimal batch size growth for wielandt method and superhistory method

Q Pan, T Zhang, X Liu, Y Cai, L Wang… - Nuclear Science and …, 2022 - Taylor & Francis
In a high dominance ratio system, the problem of slow fission source convergence is faced
during the Monte Carlo criticality calculation. The Wielandt method and the Superhistory …