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- Alpha-bearing wastes; Argonne Model for Universal Solvent Extraction (AMUSE); Computer programming; Separation (Technology); Software engineering; System analysis; Systems engineering; Transuranium elements – Separation; Uranium Recovery by Extraction (UREX) (10)
- Argonne Model for Universal Solvent Extraction (AMUSE); Computer programming; Radioactive wastes – Purification; Reactor fuel reprocessing; Separation (Technology); Software engineering; System analysis; Systems engineering; Transmutation (Chemistry) (8)
- Argonne Model for Universal Solvent Extraction (AMUSE); Computer programming; Separation (Technology); Software engineering; System analysis; Systems engineering; Transuranium elements – Separation; Uranium Recovery by Extraction (UREX) (6)
- Actinide elements; Criticality (Nuclear engineering); Neutrons — Multiplicity; Radioactive waste canisters; Reactor fuel reprocessing; Separation (Technology); Shielding (Radiation); Spent reactor fuels; Transmutation (Chemistry); Transuranium elements; Uranium Recovery by Extraction (UREX) (3)
- Actinide elements – Separation; Criticality (Nuclear engineering); Nuclear fuel claddings; Radioactive substances – Separation; Separation (Technology); Transmutation (Chemistry); Transuranium elements – Separation (1)
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- Actinide elements; Criticality (Nuclear engineering); Neutrons — Multiplicity; Reactor fuel reprocessing; Separation (Technology); Spent reactor fuels; Transmutation (Chemistry); Transuranium elements (1)
- Alpha-bearing wastes (1)
- Alpha-bearing wastes; Argonne Model for Universal Solvent Extraction (AMUSE); Computer programming; Separation (Technology); Software engineering; System analysis; Systems engineering; Transuranium elements – Separation; Uranium Recovery by Extraction (UREX)al Solvent Extraction (AMUSE); Separation (Technology); System analysis; Systems engineering; Transuranium elements – Separation; Uranium Recovery by Extraction (UREX) (1)
- Alpha-bearing wastes; Argonne Model for Universal Solvent Extraction (AMUSE); Computer programming; Separation (Technology); Software engineering; System analysis; Systems engineering; Transuranium elements – Separation; Uranium Recovery by Extraction (UREX)al Solvent Extraction (AMUSE); Separation (Technology); Systems engineering; Transuranium elements – Separation; Uranium Recovery by Extraction (UREX) (1)
- Americium; Cesium; Criticality (Nuclear engineering); Curium; Neptunium; Plutonium; Radioactive wastes; Separation (Technology); Shielding (Radiation); Strontium; Uranium Recovery by Extraction (UREX) (1)
- Criticality (Nuclear engineering) (1)
- Criticality (Nuclear engineering); Neutrons — Multiplicity; Radioactive wastes; Separation (Technology); Spent reactor fuels; Transmutation (Chemistry) (1)
- Criticality (Nuclear engineering); Radioactive wastes; Separation (Technology); Spent reactor fuels; Transmutation (Chemistry) (1)
- Nitric acid (1)
- Nitric acid; Plutonium; Radioactive wastes – Purification; Separation (Technology); Speciation (Chemistry); Tributyl phosphate; Uranium (1)
- Plutonium (1)
- Radioactive waste canisters (1)
- Radioactive wastes – Purification (1)
- Separation (Technology) (1)
- Spent reactor fuels (1)
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- Uranium (1)
Articles 31 - 37 of 37
Full-Text Articles in Nuclear Engineering
Nuclear Criticality, Shielding, And Thermal Analyses Of Separations Processes For The Transmutation Fuel Cycle, William Culbreth, Denis Beller
Nuclear Criticality, Shielding, And Thermal Analyses Of Separations Processes For The Transmutation Fuel Cycle, William Culbreth, Denis Beller
Separations Campaign (TRP)
The remediation of nuclear waste created by conventional fission reactors will rely upon the separation of the waste products for further treatment. The UREX+ process now under review will involve the use of an aqueous chemical process to separate out depleted uranium resulting in a product containing minor actinides, fission products, cesium, strontium, technetium, and iodine. The radioactive decay of strontium and cesium produces roughly half of the thermal and gamma production in spent fuel and the relatively short halflife of isotopes of both of these elements requires storage for about 300 years before heat and radiation decreases to safe …
Nuclear Criticality Analyses Of Separations Processes For The Transmutation Fuel Cycle, William Culbreth, Pang Tao, Denis Beller
Nuclear Criticality Analyses Of Separations Processes For The Transmutation Fuel Cycle, William Culbreth, Pang Tao, Denis Beller
Separations Campaign (TRP)
The separation and partitioning of used commercial reactor fuel is a vital component of any reprocessing or transmutation strategy. To process the high actinide fuels required for a transmutation effort, the Chemical Technology Division (CMT) at Argonne National Laboratory (ANL) is developing a pyrochemical separations process. Currently, this work is being done via small experiments. While this is more than sufficient to develop the technologies required to process actinide-bearing fuels, it does not allow for the direct investigation of criticality concerns that would be present in larger systems. As the volume of waste to be treated increases, a higher probability …
Nuclear Criticality Analyses Of Separations Processes For The Transmutation Fuel Cycle: Quaterly Report, William Culbreth, Pang Tao
Nuclear Criticality Analyses Of Separations Processes For The Transmutation Fuel Cycle: Quaterly Report, William Culbreth, Pang Tao
Separations Campaign (TRP)
During the first quarter of the work, the tasks included training students in the use of Monte Carlo codes used in radiation transport studies and the assessment of neutron multiplication factors for specific problems outlined by ANL-East through Drs. Laidler and Vandegrift.
The proposal also included objectives for the first year of work on this project, as listed below. The work conducted in the first quarter of the project was in partial completion of these objectives.
• Train UNLV students in the use of SCALE and/or MCNP for the assessment of nuclear criticality.
• Assess neutron multiplication factor, keff …
Development Of A Systems Engineering Model Of The Chemical Separations Process: Quarterly Progress Report 8/16/01- 11/15/01, Yitung Chen, Randy Clarksean, Darrell Pepper
Development Of A Systems Engineering Model Of The Chemical Separations Process: Quarterly Progress Report 8/16/01- 11/15/01, Yitung Chen, Randy Clarksean, Darrell Pepper
Separations Campaign (TRP)
The AAA program is developing technology for the transmutation of nuclear waste to address many of the long-term disposal issues. An integral part of this program is the proposed chemical separations scheme.
Two activities are proposed in this Phase I task: the development of a systems engineering model and the refinement of the Argonne code AMUSE (Argonne Model for Universal Solvent Extraction). The detailed systems engineering model is the start of an integrated approach to the analysis of the materials separations associated with the AAA Program. A second portion of the project is to streamline and improve an integral part …
Assessment Of Criticality Safety For Cylindrical Containers To Be Used In The Processing Of Spent Fuel, William Culbreth, Daniel R. Lowe, Jason Viggato
Assessment Of Criticality Safety For Cylindrical Containers To Be Used In The Processing Of Spent Fuel, William Culbreth, Daniel R. Lowe, Jason Viggato
Separations Campaign (TRP)
The UREX process separates uranium from transuranic wastes (TRU) and fission products (FP). Nuclear reactors require fissile isotopes that will absorb neutrons and break apart into smaller nuclei while releasing a large amount of energy as well as multiple neutrons. Fissile isotopes in spent fuel include not only 235U, but also 239Pu, 241Pu, and several isotopes of americium (Am) and curium (Cm).
TRU contains the actinides with atomic numbers greater than that of uranium. This includes Pu, Np, Am, and Cm. When TRU is separated from uranium, the TRU still poses a significant risk of sustaining a …
Nuclear Criticality Analyses Of Separations Processes For The Transmutation Fuel Cycle, William Culbreth, Pang Tao
Nuclear Criticality Analyses Of Separations Processes For The Transmutation Fuel Cycle, William Culbreth, Pang Tao
Separations Campaign (TRP)
To mitigate the waste created by conventional fission reactors, spent nuclear fuel must be mechanically separated from its cladding. For the development of fuel processing technology to support the Advanced Accelerator Applications (AAA) Program, aqueous and pyrochemical processes will be used to further separate technetium and iodine, uranium and the higher actinides (see Figure 1 for an example of the process layout)1. The higher actinides, including plutonium, americium, curium, and neptunium will be separated from the waste to facilitate their fabrication into new fuel for placement in a transmuter. High-energy neutrons generated by spallation in the transmuter break down these …
Development Of A Systems Engineering Model Of The Chemical Separations Process, Yitung Chen, Darrell Pepper, Randy Clarksean
Development Of A Systems Engineering Model Of The Chemical Separations Process, Yitung Chen, Darrell Pepper, Randy Clarksean
Separations Campaign (TRP)
Two activities are proposed: the development of a Systems Engineering model and the refinement of the Argonne code AMUSE (Argonne Model for Universal Solvent Extraction). The detailed systems engineering model will be the start of an integrated approach to the analysis of the materials separations associated with the national AAA program. A second portion of the project will streamline and improve an integral part of the overall systems model, which is the software package AMUSE. AMUSE analyzes the UREX process and other related solvent extraction processes and defines many of the process streams that are integral to the systems engineering …