Separative performance transients in a gas centrifuge

Journal Article · Sun Jul 01 00:00:00 EDT 1979 · Nucl. Technol.; (United States)

OSTI ID:6116894

Olander, D R

A general method has been developed to calculate the behavior of the exit compositions from a gas centrifuge under unsteady conditions. The method utilizes the basic enrichment gradient equations derived by Cohen, which, in this case, contain time derivatives of the partial /sup 235/U inventories. These partial differential equations are converted to ordinary differential equations by a linear approximation to the axial concentration distribution for use in the inventory terms only. With this simplification, analytical solution is possible for the feed concentration transient. The transient driven by a change in the feed flow rate, however, requires numerical solution. For analysis of ideal cascades in the unsteady state, the transient flow and separation characteristics of the centrifuge must be combined with total uranium and /sup 235/U material balances on each stage.

• Research Organization: Univ. of California, Berkely
• OSTI ID: 6116894
• Journal Information: Nucl. Technol.; (United States), Vol. 44:2
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
GAS CENTRIFUGES
TRANSIENTS
URANIUM 235
GAS CENTRIFUGATION
DIFFERENTIAL EQUATIONS
FLOW RATE
GAS FLOW
PERFORMANCE
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
CENTRIFUGATION
CENTRIFUGES
CONCENTRATORS
EQUATIONS
EVEN-ODD NUCLEI
FLUID FLOW
HEAVY NUCLEI
ISOMERIC TRANSITION ISOTOPES
ISOTOPE SEPARATION
ISOTOPES
MINUTES LIVING RADIOISOTOPES
NUCLEI
RADIOISOTOPES
SEPARATION PROCESSES
URANIUM ISOTOPES
YEARS LIVING RADIOISOTOPES
050502* - Nuclear Fuels- Uranium Enrichment- Centrifugation- (-1989)