Results 11 to 20 of about 898 (171)

An Efficient Scheme for Coupling OpenMC and FLUENT with Adaptive Load Balancing

Science and Technology of Nuclear Installations, 2021
This paper develops a multi-physics interface code MC-FLUENT to couple the Monte Carlo code OpenMC with the commercial computational fluid dynamics code ANSYS FLUENT.
Qingyang Zhang, Tianji Peng, Guangchun Zhang, Jie Liu, Xiaowei Guo, Chunye Gong, Bo Yang, Xukai Fan   +7 more
doaj   +2 more sources

OpenMC(TD): Current status and next development stages [PDF]

EPJ Web of Conferences
This work presents the current state and the next stages in the development of the modified code OpenMC(TD), a modified version of the Monte Carlo code OpenMC which includes the time dependence related to the emission of β-delayed neutrons, but instead ...
Romero-Barrientos Jaime, Molina Francisco, Zambra Marcelo, López-Usquiano Franco   +3 more
doaj   +2 more sources

Simulation of NuScale-Like SMR Benchmark with OpenMC Code

Journal of Nuclear Engineering
Compared to traditional large-scale reactors, the more heterogeneous, boron-free SMR cores create additional challenges for accurate multiphysics simulations. Therefore, advanced modelling and simulation tools should be used to create high-fidelity, high-
Abdo Ez Aldeen, Dzianis Litskevich, Christopher Grove, Seddon Atkinson, Anna Detkina, Hasnain Gulzar   +5 more
doaj   +2 more sources

Neutronics and burnup analysis of VVER-1000 LEU and MOX assembly computational benchmark using OpenMC Code [PDF]

Nuclear Energy and Technology, 2022
A handful of computational benchmarks that incorporate VVER-1000 assemblies having low enriched uranium (LEU) and the mixed oxide (MOX) fuel have been put forward by many experts across the world from the Nuclear Energy Agency.
Md. Imtiaj Hossain, Yasmin Akter, Mehraz Zaman Fardin, Abdus Sattar Mollah   +3 more
doaj   +3 more sources

Neutronic calculations for the VVER-1000 MOX core computational benchmark using the OpenMC code [PDF]

Nuclear Energy and Technology, 2023
The goal of this study is to perform neutronic calculations of the VVER-1000 MOX core computational benchmarks with an OpenMC code along with ENDF/B-VII.1 nuclear data library.
Md Imtiaj Hossain, Abdus Sattar Mollah, Yasmin Akter, Mehraz Zaman Fardin   +3 more
doaj   +3 more sources

VERIFICATION OF THE OpenMC HOMOGENIZED MYRRHA-1.6 CORE MODEL [PDF]

EPJ Web of Conferences, 2021
The OpenMC code is being employed both as a multi-group nodal macroscopic cross-section generator and a reference multi-group Monte Carlo (MGMC) solution.
Hernandez-Solis Augusto, Molla Yohannes, Malambu Edoaurd, Stankovskiy Alexey, Van den Eynde Gert   +4 more
doaj   +1 more source

Validation of the Physical Parameters of Monte Carlo Code Openmc by Unk Code for Different VVER 1200 Fuel Assemblies

Глобальная ядерная безопасность, 2022
Новый код Монте-Карло под названием OpenMC был разработан Массачусетским технологическим институтом. В данной работе рассматривается проверка детерминированного транспортного кода решетки реактора OpenMC для различных типов тепловыделяющих сборок ВВЭР ...
H. A. Tanash, D. A. Solovyev, V. G. Zimin, A. A. Semenov, N. V. Schukin, B. .. Djaroum, A. I. Al-Shamayleh   +6 more
doaj   +1 more source

Selecting Burnup Algorithms in OpenMC Using the Calculated Benchmark of LEU Assembly and MOX Fuel

Глобальная ядерная безопасность, 2023
OpenMC is a state-of-the-art Monte Carlo neutron transport simulation code that uses the Python programming language as an API. OpenMC supports eight burnout simulation algorithms.
Hamza A Tanash, Denis A Solovyov, Vyacheslav G Zimin, Alexey L Lobarev, Denis A Plotnikov, Nikolay V Schukin   +5 more
doaj   +1 more source

Comparison and verification of NECP-X and OpenMC using high-fidelity BEAVRS benchmark models

He jishu, 2022
BackgroundWith the improvement of the understanding of the physical mechanism of neutron transport and the development of high performance computing technology, high-fidelity neutronics calculation has attracted widespread attention worldwide.
SHEN Zhirui, SUN Qizheng, HE Donghao, PAN Qingquan, ZHANG Tengfei, PENG Lianghui, YANG Weiyan   +6 more
doaj   +1 more source

The Influence Mechanism of Space‐Time Kinetics of ADS Subcritical Reactor under Beam Transients

International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023
The space‐time kinetics of ADS Subcritical Reactor (ADSR) under beam transients play an important role in ensuring the reliability of the control and safety system of the accelerator‐driven subcritical system (ADS). In order to elucidate the effect of high heterogeneity of neutron flux density in space‐time on the neutron space‐time kinetics of ADSR ...
Nian-Biao Deng, De-Xin Ding, Jin-Sen Xie, Tao Yu, Cheng Hou, Alexey Mikhaylov   +5 more
wiley   +1 more source