Web8 de jun. de 2024 · If I just execute openmc in standalone mode with this xml files, then the code actually is able to run successfully the transport calculation (so the first transport calculation at burnup 0,... WebOpenMC is a community-developed Monte Carlo neutron and photon transport code. It is capable of performing fixed source, k-eigenvalue, and subcritical multiplication calculations on models built using either a constructive solid geometry or CAD representation.
Burnup dependent Monte Carlo neutron physics ... - ScienceDirect
Web9 de jul. de 2024 · OpenMC provides the power distribution within the pebbles, which is then transferred to BISON for accurate fuel performance calculations. The highly turbulent coolant flow field and heat transfer are solved using a … WebIn the axial direction, 200 cm height FAs are evenly separated into three zones, labelled as burn-up zone 1–3 from top to bottom. Each burn-up zone was filled with a specially defined fuel material. Assuming full power operating time for each calculation is 1129 days, longer than 36 months. portability computing
The standard depletiondecay problem is to predict nuclide - 豆丁网
Web1 de jan. de 2024 · In this study, OpenMC was used for core calculation to provide neutron flux, power density and nuclide microscopic reaction rate. The extended burnup equation was solved by an open source software package of computing matrix exponentials named EXPOKIT (Sidje, 1998). WebONIX — Python-based burnup code; OpenMC — Depetion solver integrated in OpenMC; radioactivedecay — Radioactive decay solver; Kinetics. KOMODO — Nuclear reactor simulator that solves 3-D diffusion using nodal methods; PyRK — Neutronic and thermal hydraulic reactor transient analysis in 0-D WebA subcriticality measuring device for spent nuclear fuel, etc., capable of reducing costs and estimating a neutron multiplication factor, which is a function of the second step. A first step of measuring the neutron count of the spent nuclear fuel to measure the burnup, and a second step of measuring the spent nuclear fuel that does not satisfy the burnup limit … portability computers