Dec 2, 2024 · In NECP-MCX V1.0, the Constructive Solid Geometry (CSG) is used, which can handle complex geometries theoretically. However, plenty of human effect is needed to build …

To save memory consumption, the functionality of building a hybrid CSG-UM model was developed in NECP-MCX V2.0. The CSG model and the UM model are built separately by the …

Nov 5, 2024 · NECP-MCX is a Monte-Carlo particle-transport code developed by the Nuclear Engineering Computational Physics (NECP) Lab. of Xi’an Jiaotong University in 2018. The first …

Jul 18, 2023 · This approach presents a significant advantage over the traditional Constructive Solid Geometry (CSG)–based MC method in handling complex geometries and conducting …

In this work, we report a modern, scalable, high-performance, and fully open-source in-browser MC simulation platform—MCX Cloud—to bring state-of-the-art GPU hardware and our …

Feb 22, 2025 · SuperMC/MCAM uses a BRep-to-CSG conversion method based on feature recognition. It identifies the topological and geometric features in geometric solids represented …

SuperMC/MCAM uses a BRep-to-CSG con-version method based on feature recognition. It identifies the topological and geometric features in geometric solids represented by BRep …

Dec 1, 2024 · The Monte Carlo (MC) method solves the neutron transport calculation with flexible Constructive Solid Geometry (CSG) and continuous-energy nuclear data. Therefore, the MC …

NECP-MCX is a Monte-Carlo particle-transport code developed by the Nuclear Engineering Computational Physics (NECP) Lab. of Xi’an Jiaotong University in 2018. The first version of …

NECP-MCX is aimed at the simulation of deep-penetration problems, including reactor radiation-shielding calculation, fusion reactor blanket calculation, etc. These problems are challenging …