4/12/2023 0 Comments Depletion per unit calculator![]() ![]() Reaction to be listed multiple times with different branching ratios resulting However, the depletion chain file does allow a transmutation OpenMC’s transport solver does not currently allow energy-dependent captureīranching ratios. This isĬomplicated by the fact that the branching ratio may depend on the incident Has a significantly longer half-life than the ground state, it is important toĪccurately model the branching of the capture reaction in Am241. Which can produce either Am242 or Am242m. The most well-known example is capture in Am241, Some (n, \(\gamma\)) reactions may result in a product being in either the The pregenerated chain files that are available on ![]() Reaction that is present in both the available cross sections and the depletionĬhain file. Transport-independent depletion, OpenMC will calculate reaction rates for every What transmutation reactions are available in a depletion chain file, so anyĪrbitrary number of transmutation reactions can be tracked. In transport-coupled depletion, OpenMC will setup tallies in a problem based on If a nuclide is fissionable, the fission products yields at any number of If a nuclide is not stable, what decay modes are possible, their branching What transmutation reactions are possible, their Q values, and their products In OpenMC, the burnup matrix is constructedīased on data inside of a depletion chain file, which includes fundamentalĭata gathered from ENDF incident neutron, decay, and fission product yield Sections (in the case of transport-independent depletion), but also a series ofĬhoices about what data to include. (in the case of transport-coupled depletion) or to obtain microscopic cross Only solving the transport equation to estimate transmutation reaction rates However, constructing the burnup matrix itself involves not Just construct the burnup matrix at various times and solve a set of sparse The \(k\)th order approximation for CRAM requires solving \(k/2\) ![]()
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