Results 71 to 80 of about 538 (156)

Pre-release of OpenMC 0.6.0

open access: yes, 2014
<a name="user-content-new-features" class="anchor" href="#new-features"></a>New Features <ul> <li>Legendre and spherical harmonic expansion tally scores</li> <li>CMake is now default build system</li> <li> ...
tpviitan   +7 more
core   +1 more source

VNS Tokamak OpenMC-Serpent Validation for Medical Isotope Studies

open access: yesCoRR
The Volumetric Neutron Source (VNS) tokamak is a proposed fusion reactor for testing and qualification of reactor components for future use in a fusion power facility, and has potential use for radioisotope production. The VNS geometry is modeled in the Serpent and OpenMC neutronics codes.
Christopher Ehrich   +3 more
openaire   +2 more sources

Development of an Event Tracking Feature in OpenMC for Neutron Noise Analysis [PDF]

open access: yesEPJ Web of Conferences
We present the development and implementation of a neutron event-tracking capability in OpenMC, an open-source, community-driven Monte Carlo radiation transport code.
Saliba Michel   +5 more
doaj   +1 more source

Benchmarking of probability tables with TRIPOLI-5® [PDF]

open access: yesEPJ Web of Conferences
In this work we present the verification of the unresolved resonance range treatment implementation in the Monte Carlo code TRIPOLI-5®, which relies on probability tables.
Montecchio Cecilia   +3 more
doaj   +1 more source

Modeling Decay Heat with a Simplified Depletion Chain in OpenMC

open access: yesTransactions of the American Nuclear Society
OpenMC can be used to computationally model depletion and produce estimates of decay heat. As an input to depletion simulations, OpenMC requires a depletion chain that details nuclide transmutation pathways. The simplified CASL depletion chain was designed to track relatively few nuclides while still accurately modeling the effective neutron ...
Gupta, Tanmay, Forget, Benoit
openaire   +2 more sources

Distributed OpenMP Offloading of OpenMC on Intel GPU MAX Accelerators

open access: yesCoRR
Monte Carlo (MC) simulations play a pivotal role in diverse scientific and engineering domains, with applications ranging from nuclear physics to materials science. Harnessing the computational power of high-performance computing (HPC) systems, especially Graphics Processing Units (GPUs), has become essential for accelerating MC simulations. This paper
Fridman, Yehonatan   +3 more
openaire   +2 more sources

Development of BNCT Dose Calculation Function Based on cosRMC

open access: yesJournal of Isotopes
To ensure the effectiveness and safety of boron neutron capture therapy (BNCT),precise dose calculation and treatment planning are of critical importance.
Shengzhe WANG   +5 more
doaj   +1 more source

CAD and constructive solid geometry modeling of the Molten Salt Reactor Experiment with OpenMC

open access: yesFrontiers in Nuclear Engineering
In this study, we present a detailed comparison of two independently developed models of the Molten Salt Reactor Experiment (MSRE) for Monte Carlo particle transport simulations: the constructive solid geometry (CSG) model that was developed in support ...
Seda Yilmaz   +4 more
doaj   +1 more source

Multi-step verification of the Copenhagen atomics molten salt experiment radioactive inventory at the Paul Scherrer Institute using OpenMC, Serpent, and EQL0D

open access: yesFrontiers in Nuclear Engineering
The molten salt experiment (MSE) is a 30-day 1 MW (thermal) molten salt criticality experiment designed by Copenhagen Atomics that will be conducted at the Paul Scherrer Institute (PSI) Swiss research center.
Lorenzo Chierici, Alessio Rossi
doaj   +1 more source

Transmutation of MAs and LLFPs with a lead-cooled fast reactor. [PDF]

open access: yesSci Rep, 2023
Sun XY   +5 more
europepmc   +1 more source

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