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- #Lightwright 6 how do i get load calculation software#
- #Lightwright 6 how do i get load calculation code#
- #Lightwright 6 how do i get load calculation download#
Posted by admin ApApPosted in Advanced modeling, data processing and simulation tools Post navigation Definition of a shielding device to reduce the activation ĭesign of local shielding of IFMIF-EVEDA beam dump : Analysis of the limiting dose points in an existing facility building in order to optimize the shielding elements. Calculation of dose at operation and after shutdown.
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Preliminary design of IFMIF beam dump: Conceptual design of the IFMIF facility defining the thickness of the building walls around and the ceiling over accelerator beam dump. SEA have been working with CIEMAT on the calculation of activation and dose maps around the beam dump to optimize the design of IFMIF define the proper local shielding device : There is a strong need in fusion research to calculate the activation of the structures for the design of TBM shielding modules in order to meet the requirements of residual dose to operators 12 days after reactor shutdown. Criticality safety with credit to burnup. The overall capabilities of this solution in fusion research and beyond include: §Design of shielding elements and materials, design of buildings layout for the installation of sources, Analysis of neutron damage, neutron activation, neutron heating and gas production §Analysis of residual dose at shutdown due to the neutron activation of the shielding materials and of the components near the neutron source, Determination of residual dose maps §Isotopic evolution of fission reactor fuel along depletion Shielding of spent fuel assemblies. This solution could find promising applications in nuclear fission (analysis of the activation and residual dose produced by metallic components inside reactor vessel), dismantling operations (inside reload cavity) or in healthcare (prevention and reduction of radiations exposures during medical treatment). §The system works in reasonable time frame for arrays smaller than 100×100 voxels each layer (Beyond that the activation process and the interactive mode is not practical). §Simplifies the strict process of “neutron flux-activation calculation-residual dose” calculation by using highly visible geometry arrays and keeping control of the whole calculation process without the risks of “black box” use of other solutions. Highly specialized in the analysis of radiation transport problem by the use of three-dimensional Monte Carlo tools, mainly MCNP (Monte Carlo N-Particle) family of codes.
#Lightwright 6 how do i get load calculation code#
The wide experience with the use of MCNP and ACAB (Activation Abacus Code) codes allows the creation and easy use of this program instead of the long processing times of automated routines using MCNP+FISPACT (inventory code capable of performing modelling of activation, transmutations and depletion induced by neutron, proton, alpha, deuteron or gamma particles incident on matter).
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It is being used in metallic components inside fission reactor vessel and inside reload cavity during dismantling operations. The process of automation and residual dose calculation may take 1 hour for a 15 layers case of such 50×50 voxels array. It also provides the source distribution of photons produced in the decay of such nuclides and calculate the dose around the structure produced by the different nuclides. It decomposes the 3D geometry in a set of layers of approximately 50×50 voxels and allows using the energy-detailed neutron flux in these voxels to determine the activity of nuclides of interest at each layer.
#Lightwright 6 how do i get load calculation software#
The technology consists in a software which automates the process of calculation of neutron activation of a structure or component and the residual dose around this structure or component.
#Lightwright 6 how do i get load calculation download#
DOWNLOAD THE TECHNOLOGY DESCRIPTION Description of the Technology