A coprocessing solvent extraction flowsheet for recovering and purifying LWR fuels has been altered to achieve partial partioning of uranium and plutonium to eliminate streams with pure plutonium. Partial partitioning has been demonstrated in the laboratory with simulated feeds and irradiated LWR fuel solutions. Hydroxylamine nitrate was the reductant in these tests. Plutonium was concentrated by factors of 6 to 27.4. Tests have shown that 1 to 2 plutonium atoms are reduced for each hydroxylamine molecule consumed. Nitrite interferes with the reduction of plutonium, unless the hydroxylamine concentration is increased. 12 tables, 11 figures
International audienceIn the framework of the development of Generation IV reactors, innovative solv...
Laboratory studies, followed by plant operation, established that a mixture of hydroxylamine nitrate...
In solvent extraction purification processes such as are used at Hanford, the fuel elements or "slug...
Coprocessing solvent extraction studies using irradiated LWR and FBR fuels have indicated the need f...
Initial runs were completed in a new solvent extraction facility that has been built for testing cop...
Experiments on tri-n-butyl phosphate solvent extraction of uranium and plutonium at full activity le...
In Campaign 5, fast breeder reactor (FBR) fuel [average burnup {similar_to}2.6 TJ/kg ({similar_to}30...
The Solvent Extraction Test Facility (SETF) was installed in one of the heavily shielded cells of th...
Two solvent extraction experiments were made in the Solvent Extraction Test Facility (SETF) during C...
In order to recycle potentially valuable uranium and plutonium, the Purex process has been successfu...
A series of five solvent extraction tests were made in the Solvent Extraction Test Facility (SETF) d...
The Nuclear Power Development Division (NPD) under the Assistant Secretary for Energy Technology in ...
The initial motivation for the development of reprocessing technologies was to obtain pure fissile m...
In Campaign 8, two batches of irradiated fuel from the Fast Flux Test Facility (FFTF) were processed...
The initial motivation for the development of reprocessing technologies was to obtain pure fissile m...
International audienceIn the framework of the development of Generation IV reactors, innovative solv...
Laboratory studies, followed by plant operation, established that a mixture of hydroxylamine nitrate...
In solvent extraction purification processes such as are used at Hanford, the fuel elements or "slug...
Coprocessing solvent extraction studies using irradiated LWR and FBR fuels have indicated the need f...
Initial runs were completed in a new solvent extraction facility that has been built for testing cop...
Experiments on tri-n-butyl phosphate solvent extraction of uranium and plutonium at full activity le...
In Campaign 5, fast breeder reactor (FBR) fuel [average burnup {similar_to}2.6 TJ/kg ({similar_to}30...
The Solvent Extraction Test Facility (SETF) was installed in one of the heavily shielded cells of th...
Two solvent extraction experiments were made in the Solvent Extraction Test Facility (SETF) during C...
In order to recycle potentially valuable uranium and plutonium, the Purex process has been successfu...
A series of five solvent extraction tests were made in the Solvent Extraction Test Facility (SETF) d...
The Nuclear Power Development Division (NPD) under the Assistant Secretary for Energy Technology in ...
The initial motivation for the development of reprocessing technologies was to obtain pure fissile m...
In Campaign 8, two batches of irradiated fuel from the Fast Flux Test Facility (FFTF) were processed...
The initial motivation for the development of reprocessing technologies was to obtain pure fissile m...
International audienceIn the framework of the development of Generation IV reactors, innovative solv...
Laboratory studies, followed by plant operation, established that a mixture of hydroxylamine nitrate...
In solvent extraction purification processes such as are used at Hanford, the fuel elements or "slug...