Modeling of UF{sub 6} enrichment with gas centrifuges for nuclear safeguards activities
- European Commission, Joint Research Centre, Institute for Transuranium Elements Via Fermi, 2749-TP181,20127 Ispra (Italy)
The physical modeling of uranium isotopes ({sup 235}U, {sup 238}U) 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 UF{sub 6} 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.
- OSTI ID:
- 22075543
- Journal Information:
- AIP Conference Proceedings, Vol. 1479, Issue 1; Conference: ICNAAM 2012: International Conference of Numerical Analysis and Applied Mathematics, Kos (Greece), 19-25 Sep 2012; Other Information: (c) 2012 American Institute of Physics; Country of input: International Atomic Energy Agency (IAEA); ISSN 0094-243X
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
98 NUCLEAR DISARMAMENT
SAFEGUARDS AND PHYSICAL PROTECTION
CENTRIFUGATION
COMPUTERIZED SIMULATION
GAS CENTRIFUGES
HYDRODYNAMICS
ISOTOPE SEPARATION PLANTS
M CODES
NUCLEAR FUELS
REACTOR FUELING
SAFEGUARDS
SIMULATORS
SPATIAL DISTRIBUTION
T CODES
URANIUM 235
URANIUM 238
URANIUM HEXAFLUORIDE