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|Title:||Modeling of UF6 Enrichment with Gas Centrifuges for Nuclear Safeguards Activities|
|Authors:||MERCURIO GIOVANNI; PEERANI Paolo; RICHIR Patrice; JANSSENS Willem; EKLUNDH Lars|
|Citation:||10th International Conference of Numerical Analysis and Applied Mathematics - ICNAAM 2012 p. 201 - 204|
|Publisher:||American Institute of Physics|
|Type:||Articles in periodicals and books|
|Abstract:||The physical modeling of uranium isotopes (235U, 238U) separation process by centrifugation of is a key aspect for predicting the nuclear fuel enrichment plant performances under surveillance by the Nuclear Safeguards Authorities. In this paper are illustrated some aspects of the modeling of fast centrifuges for UF6 gas enrichment and of a typical cascade enrichment plant with the Theoretical Centrifuge and Cascade Simulator (TCCS). The background theory for reproducing the flow field characteristics of a centrifuge is derived from the work of Cohen  where the separation parameters are calculated using the solution of a differential enrichment equation. In our case we chose to solve the hydrodynamic equations for the motion of a compressible fluid in a centrifugal field using the Berman – Olander vertical velocity radial distribution  and the solution was obtained using the Matlab software tool . The importance of a correct estimation of the centrifuge separation parameters at different flow regimes, lies in the possibility to estimate in a reliable way the U enrichment plant performances, once the separation external parameters are set (feed flow rate and feed, product and tails assays). Using the separation parameters of a single centrifuge allow to determine the performances of an entire cascade and, for this purpose; the software Simulink  was used. The outputs of the calculation are the concentrations (assays) and the flow rates of the enriched (product) and depleted (tails) gas mixture. These models represent a valid additional tool, in order to verify the compliance of the U enrichment plant operator declarations with the “on site” inspectors’ measurements.|
|JRC Directorate:||Nuclear Safety and Security|
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