Results 51 to 60 of about 538 (156)

Multiphysics Analysis of Natural Circulation‐Driven Operation of Passive Molten Salt Fast Reactor and Effect of Guide Structure

International Journal of Energy Research, Volume 2025, Issue 1, 2025.
A new molten salt reactor (MSR) design has been developed aiming for long‐term operation and high safety. In order to enhance the integrity and economy of the system during the long‐term operation, pumps were removed from the primary system, and the fuel salt flow was developed by natural circulation.
Juhyeong Lee, Min Seop Song, Seungug Jae, Won Sik Yang, Sung Joong Kim, Mahmoud Ahmed   +5 more
wiley   +1 more source

OpenMC 0.6.1

, 2014
<p>New Features</p> <ul> <li>Coarse mesh finite difference (CMFD) acceleration no longer requires PETSc</li> <li>Statepoint file numbering is now zero-padded</li> <li>Python scripts now compatible with ...
Jon Walsh (8259438), Tuomas Viitanen (8259447), Nicholas Horelik (8259435), Sterling Harper (8259441), Bryan Herman (8259432), Paul Romano (664936), Nicholas Horelik, Jon Walsh, Will Boyd, Will Boyd (8259444), Tuomas Viitanen, Adam Nelson (68165), Bryan Herman, Sterling Harper, Adam Nelson, Paul Romano   +15 more
core   +1 more source

Extending OpenMC validation to spent fuel canisters: A criticality benchmark against MCNP

Nuclear Engineering and Technology
OpenMC is an open-source Monte Carlo code with increasing relevance in criticality safety and reactor physics applications. While its validation has covered a broad range of systems, its performance in spent nuclear fuel storage scenarios remains limited
J. Ruiz-Pineda, J. Romero-Barrientos, F. Molina, M. Zambra, F. López-Usquiano   +4 more
doaj   +1 more source

Evaluation of Improved Contribution Function Method in the Compression of CINDER90 Depletion Library

Science and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.
The improved contribution function (ICF) method based on generalized perturbation theory (GPT) is applied to the compression of CINDER90 depletion library. A series of representative problems for PWR are defined with different fuel materials and operation conditions.
Yunfei Zhang, Qian Zhang, Qiang Zhao, Yang Zou, Jian Guo, Rui Yan, Guifeng Zhu, Arkady Serikov   +7 more
wiley   +1 more source

openmc: OpenMC 0.6.2

, 2015
<a class="anchor" href="#new-features"><span class="octicon octicon-link"></span></a>New Features <ul> <li>Meshline plotting capability</li> <li>Support for plotting cells/materials on middle universe ...
tpviitan, Anton Leontiev, Locke, Matt Ellis, Nicholas Horelik, Jon Walsh, Will Boyd, John Xia, Bryan Herman, Sterling Harper, Adam Nelson, Paul Romano   +11 more
core   +1 more source

The Study of Continuous Core Zoning to Extend the Graphite Component Irradiation Lifespan in Molten Salt Reactor

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
Graphite is widely used in molten salt reactors (MSRs) because of its excellent properties. However, the irradiation lifespan of graphite in MSR is much shorter than the life of a conventional nuclear power plant, which lowers the load factor and increases the economic burden.
Shuyang Jia, Guifeng Zhu, Yang Zou, Jian Guo, Zhenghao Xu, Siqin Hu, Hongjie Xu, Sanjay Basumatary   +7 more
wiley   +1 more source

Validation of Multiphysics Simulation Using OpenFOAM–PRAGMA Coupled Code for Heat Pipe Cooled Microreactor Core With the KRUSTY Experiment

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
A heat pipe cooled microreactor (HPMR) offers advantages such as compact design, ease of transportation, and improved system reliability and safety. The core of the HPMR consists of a solid structure called a “monolith,” which contains multiple fuel rods and heat pipes (HPs).
Myung Jin Jeong, Jaeuk Im, San Lee, Hyoung Kyu Cho, Mahmoud Ahmed   +4 more
wiley   +1 more source

Neutronic Analysis of Accident‐Tolerant Cladding Materials in 3D Full Core BEAVRS PWR Benchmark Using OpenMC Code

International Journal of Energy Research, Volume 2024, Issue 1, 2024.
After the Fukushima Daiichi nuclear accident in 2011, the performance of nuclear fuel during accidents became a matter of great concern. To address this, a new type of fuel technology called accident‐tolerant fuel (ATF) has been developed with the goal of enhancing the ability of light water reactors (LWRs) to withstand severe accident conditions. Iron‐
Khalid A. Alamri, Meshari M. Alqahtani, Abdullah S. Alomari, Abdullah I. Almarshad, Andrey Kuzmin   +4 more
wiley   +1 more source

mit-crpg/openmc: OpenMC 0.9.0

, 2017
<p>This release of OpenMC is the first release to use a new native HDF5 cross section format rather than ACE format cross sections. Other significant new features include a nuclear data interface in the Python API (<a href="http://openmc ...
Jingang Liang, Anthony Scopatz, Will Boyd, Jon Walsh, Nicholas Horelik, Travis L., Amanda Lund, Kelly L. Rowland, John Lyu, Locke, Qingming He, Matt Ellis, Colin Josey, John Xia, Derek Gaston, Sterling Harper, Bryan Herman, Adam Nelson, sam, Paul Romano   +19 more
core   +1 more source

Comparison of Hexagonal and Square Fuel Pin Arrangement with UN-PuN Fuel in PWR

Computational and Experimental Research in Materials and Renewable Energy
Indonesia is experiencing an increasing demand for electrical energy, which can be met through alternative sources such as nuclear energy generated in nuclear reactors at Nuclear Power Plants (NPPs).
Muhammad Syu’bi Alwi, Ratna Dewi Syarifah, M. Khanifuddin Zuhri, Wenny Maulina   +3 more
doaj   +1 more source