Separative performance transients in a gas centrifuge
Description
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 235U 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 235U material balances on each stage
Additional details
Publishing Information
- Journal Title
- Nucl. Technol.
- Journal Volume
- 44
- Journal Issue
- 2
- Series
- Nucl. Technol.
- Journal Page Range
- 307-314
- ISSN
- 0029-5450
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 11500042
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Descriptors DEI
- DIFFERENTIAL EQUATIONS; FLOW RATE; GAS CENTRIFUGATION; GAS CENTRIFUGES; GAS FLOW; PERFORMANCE; TRANSIENTS; URANIUM 235
- Descriptors DEC
- ACTINIDE NUCLEI; ALPHA DECAY RADIOISOTOPES; CENTRIFUGATION; CENTRIFUGES; EQUATIONS; EVEN-ODD NUCLEI; FLUID FLOW; HEAVY NUCLEI; ISOMERIC TRANSITION ISOTOPES; ISOTOPES; MINUTES LIVING RADIOISOTOPES; NUCLEI; RADIOISOTOPES; SEPARATION PROCESSES; URANIUM ISOTOPES; YEARS LIVING RADIOISOTOPES