Results 81 to 90 of about 538 (156)

Demonstration of OpenMC as a framework for atomic transport and plasma interaction

open access: yesPlasma Physics and Controlled Fusion
Abstract Modern tooling is demanded for predicting the transport and reaction characteristics of atoms and molecules, especially in the context of magnetic confinement fusion. DEGAS2, among the most common and capable tools currently in use, shares many fundamental similarities with the OpenMC framework, which was primarily developed for
G J Wilkie, P K Romano, R M Churchill
openaire   +2 more sources

Assessment of OpenMC for static and depletion studies of the MSFR with EVOL and SAMOSAFER benchmarks

open access: yes
LAUREA MAGISTRALEIl Reattore Veloce a Sali Fusi (MSFR) è una delle tecnologie selezionate per far parte della Generazione IV dal Generation IV International Forum.
BELOTTI, FILIPPO
core  

Multiscale computational study to predict the irradiation-induced change in engineering properties of fusion reactor materials

open access: yesNuclear Materials and Energy
In this study, we address the impact of irradiation conditions in a tokamak on the engineering properties of materials, leading to potential degradation of in-vessel components over their lifecycle.
Salahudeen Mohamed   +3 more
doaj   +1 more source

The Paramak: automated parametric geometry construction for fusion reactor designs. [PDF]

open access: yesF1000Res, 2021
Shimwell J   +6 more
europepmc   +1 more source

Application of LoongSARAX in Calculation of Plate Fuel Critical Experimental Facility

open access: yesYuanzineng kexue jishu
As the main type of fast reactor in the future development of nuclear energy, neutron calculation is very important for core design and safety analysis.
LI Zehua1, ZHANG Qian2, DU Xianan3, ZHAO Changyou1
doaj   +1 more source

Development and validation of fully open-source R2S shutdown dose rate capabilities in OpenMC

open access: yesNuclear Fusion
We present the first fully open-source capabilities for shutdown dose rate (SDR) calculations of fusion energy facilities based on the Rigorous 2-Step (R2S) methodology.
Ethan E. Peterson   +3 more
doaj   +1 more source

Nuclear and radiological characterization of a 226Ra-Be neutron irradiator at INFISA-UNMSM, Peru, using Monte Carlo simulation with the OpenMC code

open access: yesNuclear Engineering and Technology
A neutron irradiator consisting of a226Ra-Be source with a 3 mCi activity of radium, used for the early teaching of neutron activation experiments, belonging to the INFISA-UNMSM, was characterized using the relatively new open-source framework OpenMC ...
P. Tataje   +3 more
doaj   +1 more source

Neutronics Analysis on High-Temperature Gas-Cooled Pebble Bed Reactors by Coupling Monte Carlo Method and Discrete Element Method

open access: yesEnergies
The High-Temperature Gas-Cooled Pebble Bed Reactor (HTG-PBR) is notable in the advanced reactor realm for its online refueling capabilities and inherent safety features.
Kashminder S. Mehta   +2 more
doaj   +1 more source

Assemblies design and modeling analysis of a new fine mesh neutronics/thermal-hydraulics coupling benchmark for plate-type PWR core

open access: yesNuclear Engineering and Technology
In order to support the verification of neutronics/thermal-hydraulics coupling calculation method or simulation codes at the fine mesh for plate-type pressurized water reactor (PWR) with high parameters (which the ratio of power to mass flow rate is ...
Zhigang Li   +10 more
doaj   +1 more source

OpenMC modeling of the critical MYRRHA configuration : an emphasis in cross section homogenization [PDF]

open access: yes, 2019
MYRRHA-ADS is a research reactor, which is under design and development by the Belgian Nuclear Research Center, SCK•CEN. The reactor will have innovative applications such as, transmutation of high-level waste via fast spectrum, radioisotope production ...
Molla, Yohannes
core  

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