A fast breeder system concept: A diversion resistant fuel cycle

Levenson, M.; Zebroski, E.L.

doi:10.1016/0029-5493(79)90084-0

Cited by 4 publications

(3 citation statements)

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“…In the United States, the Allied Chemical Company produces UF 6 from ore concentrates in the different sequence of steps shown in Figure 4. Concentrates are reduced directly to impure U02 which is first hydrofluorinated to impure UF 4 and then fluorinated to impure UF6, which is finally purified by distillation. Conversion cost is around $5/kgU.…”

Section: Natural Uranium Conversionmentioning

confidence: 99%

The Nuclear Fuel Cycle: An Overview

Benedict

1981

Nuclear Engineering for an Uncertain Future

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Section: Natural Uranium Conversionmentioning

confidence: 99%

The Nuclear Fuel Cycle: An Overview

Benedict

1981

Nuclear Engineering for an Uncertain Future

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“…Operating conditions and results of these tests are presented in Table 11. The concentrations of uranium and H^ in the product and the waste streams are in excellent agreement with the theoretical values calculated with the Solvex code [11]. The foUowing values were obtained for decontamination factors^ of uranium from ruthenium (OF,^^) and from zirconium {DF.^^): …”

Section: Evaluation Of Centrifugal Contactors For Civex Processmentioning

confidence: 92%

“…The modification is achieved by lowering the uranium Saturation of the solvent; by ehminating the scrub section of the A extraction bank; and by Stripping plutonium together with a portion of the uranium from the organic phase in the B partition bank. One such modification, known as the Civex process, has been proposed [11]. Extraction tests were designed to evaluate the suitability of centrifugal contactors as equipment for the Civex process.…”

Section: Evaluation Of Centrifugal Contactors For Civex Processmentioning

confidence: 99%

Solvent Extraction Studies in Miniature Centrifugal Contactors

et al. 1980

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Solvent extraction IFuelreprocessinglCentrifugal contactors! Ruthenium jZirconiumThe contactor was also tested for application to the Civex and Thorex processes. SummaryA miniature short-residence-time centrifugal solvent extraction contactor and an eight-stage laboratory minibank of centrifugal contactors were used for testing the possibility of utilizing kinetic effects for improving the Separation of uranium from ruthenium and zirconium in the Purex process. Results of these tests showed that a small improvement found in ruthenium and zirconium decontamination in single-stage solvent extraction tests was lost in the multistage extraction tests -in fact, the extent of Saturation of the solvent by uranium, rather than the stage residence time, controlled the extent of ruthenium and zirconium extraction. In applying the centrifugal contactor to the Purex process, the primary advantages would be less radiolytic damage to the solvent, high throughput, reduced solvent inventory, and rapid attainment of steady-state operating conditions. The multistage mini contactor was also tested to determine the suitability of short-residence-time contactors for use with the Civex and Thorex processes and was found to be compatible with the requirements of these processes.

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LMFBR Core Materials

Roberts

1981

Structural Materials in Nuclear Power Systems

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A fast breeder system concept: A diversion resistant fuel cycle

Cited by 4 publications

References 0 publications

The Nuclear Fuel Cycle: An Overview

The Nuclear Fuel Cycle: An Overview

Solvent Extraction Studies in Miniature Centrifugal Contactors

LMFBR Core Materials

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