FIELD: atomic industry; methods of separation of uranium by the gaseous centrifugation.
SUBSTANCE: the invention is pertaining to the field of atomic industry, in particular, to the separation of uranium by the method of the gaseous centrifugation. The technical result of the invention is minimization of the losses of the separable power of the centrifugal cascades. The gaseous centrifuges cascade has: the close or equal number of centrifuges in the stages integrated by the interstage streams of circulation of the isotopic gaseous mixture; the separable streams in the separating and dumping parts of the cascade; two intercascade streams of the cascade makeup, between which there are the central part of the cascade, the critical diaphragms and-or the control valves for installation and correction of the mass consumption of the separable and intercascade streams. The preliminary optimization calculation is conducted of the cascade for definition of the matrix coefficients of the gas-dynamic properties of the stages. Then execute adjustment of the cascade for the calculated mass consumption of the transit stream of the isotopic gaseous mixture in the direction of the dumping part of the cascade by changing of the mass consumptions of the separable and-or the intercascade streams according to the results of the measuring of the isotopic concentration of the isotopic gaseous mixture of the interstage streams in the characteristic points of the cascade. Correction of mass consumptions of the streams conduct in the separable part of the cascade in proportion to the value of the relative difference of the isotopic concentrations of the interstage streams of the feeding of the stage determined according to the results of the measuring of the physical isotopic concentrations of the gaseous mixture in the interstage streams and calculated according to the definite mathematical ratio.
EFFECT: the invention ensures is minimization of the losses of the separable power of the centrifugal cascades.
6 cl, 2 dwg, 1 tbl
Title | Year | Author | Number |
---|---|---|---|
METHOD FOR GAS CENTRIFUGE CASCADE CONTROL FOR URANIUM ENRICHMENT | 2006 |
|
RU2324527C2 |
METHOD OF ENRICHING URANIUM ON CASCADE INSTALLATION | 2008 |
|
RU2405618C2 |
METHOD OF PRODUCTION OF THE LOW-ENRICHED URANIUM HEXAFLUORIDE FROM THE HIGHLY-ENRICHED URANIUM | 2005 |
|
RU2316476C2 |
METHOD FOR RECOVERING FUEL IN THE FORM OF URANIUM ISOTOPE HEXAFLUORIDE MIXTURE BURNT UP IN NUCLEAR REACTOR FOR ITS REUSE IN NUCLEAR REACTOR | 2005 |
|
RU2307410C2 |
METHOD OF PREPARING REDUCED-ENRICHMENT URANIUM HEXAFLUORIDE FROM HIGH-ENRICHMENT ARMS URANIUM | 2005 |
|
RU2292303C2 |
METHOD OF ISOTOPIC RECOVERY OF REGENERATED URANIUM | 2012 |
|
RU2497210C1 |
METHOD OF ISOTOPIC RECYCLING URANIUM | 2007 |
|
RU2361297C2 |
METHOD FOR RECOVERED-URANIUM ISOTOPE REDUCTION | 2004 |
|
RU2282904C2 |
METHOD FOR ISOTOPE RECOVERY OF REGENERATED URANIUM | 2019 |
|
RU2702620C1 |
METHOD OF PURIFYING CONTAMINATED RAW MATERIAL FOR SEPARATING PRODUCTION | 2016 |
|
RU2613157C1 |
Authors
Dates
2006-06-20—Published
2003-07-02—Filed