Results 21 to 30 of about 538 (156)

Validation of OpenMC Code for Low-cycle and Low-particle Simulations in the Neutronic Calculation

JIF (Jurnal Ilmu Fisika)
Validation of Low-Cycle and Low-Particle OpenMC Simulation Codes for Neutronics Calculations has been conducted. This study validates OpenMC, an evolving open-source neutron analysis code.
Ahmad Muzaki Mabruri, Ratna Dewi Syarifah, Indarta Kuncoro Aji, Artoto Arkundato, Nuri Trianti   +4 more
doaj   +3 more sources

Discrepancy across various OpenMC versions due to thermal neutron scattering law [PDF]

EPJ Web of Conferences
The performance of neutron transport calculations is heavily reliant on the fidelity of nuclear data. The Free Gas Model (FGM) is no longer applicable at low neutron energy range due to nucleus binding effects, necessitating the implementation of the ...
Wang Tianxiang, Chen Shengli, Xu Shuqi, Li Zhuo   +3 more
doaj   +2 more sources

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

High‐Fidelity Monte Carlo Analysis of Highly‐Localized Fission Power Peaking near a Flux Trap in an MTR Core

International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023
In this study, a high‐fidelity Monte Carlo model was utilized to investigate the localized behavior of the power peaking factor in a reactor core. The model considered the effect of water gaps, also known as flux traps, on the local power peaking.
Hadi Abuzlf, Christian Castagna, Tzach Makmal, Ofer Aviv, Zohar Yungrais, Guy Gabrieli, Uri Steinitz, Izhar Neder, Erez Gilad, Sathish K. Kamaraj   +9 more
wiley   +1 more source

Progress and Status of the Openmc Monte Carlo Code [PDF]

The present work describes the latest advances and progress in the development of the OpenMC Monte Carlo code, an open-source code originating from the Massachusetts Institute of Technology. First, an overview of the development workflow of OpenMC is given. Various enhancements to the code such as real-time XML input validation, state points, plotting,
Siegel, Andrew R., Romano, Paul Kollath, Herman, Bryan R, Horelik, Nicholas Edward, Forget, Benoit Robert Yves, Smith, Kord S.   +5 more
openaire   +2 more sources

openmc-dagmc-wrapper. A Python package for performing standard neutronics simulations with OpenMC and DAGMC

, 2021
What's Changed Fix 2D mesh resolution by @RemDelaporteMathurin in https://github.com/fusion-energy/openmc-dagmc-wrapper/pull/93 Removed unused imports by @RemDelaporteMathurin in https://github.com/fusion-energy/openmc-dagmc-wrapper/pull/92 Wrapping ...
Shimwell, Jonathan, Delaporte-Mathurin, Rémi   +1 more
core   +1 more source

openmc-dev/openmc: OpenMC 0.13.3

, 2023
This release of OpenMC includes many bug fixes, performance improvements, and several notable new features. Some of the highlights include support for MCPL source files, NCrystal thermal scattering materials, and a new openmc.stats.MeshSpatial class that
Isaac Meyer, Jiankai, Lewis Gross, Kalin Kiesling, Olek, Jonathan Shimwell, John Tramm, YoungHui Park, Patrick Myers, Andrew Johnson, Zhuoran Han, sam, Ethan Peterson, Jingang Liang, April Novak, dryuri92, Nicholas Horelik, Amanda Lund, Josh May, Erik B Knudsen, Guillaume Giudicelli, Olaf Schumann, Gavin Ridley, Miriam Kreher, Sterling Harper, Andrew Davis, Adam Nelson, Patrick Shriwise, Rémi Delaporte-Mathurin, Paul Romano   +29 more
core   +1 more source