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). 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. 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. DOWNLOAD THE TECHNOLOGY DESCRIPTION Description of the Technology
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