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| Author | : Gerald Craig Swanson |
| Publisher | : |
| Total Pages | : 260 |
| Release | : 1975 |
| Genre | : Oxides |
| ISBN | : |
| Author | : |
| Publisher | : |
| Total Pages | : |
| Release | : 1975 |
| Genre | : |
| ISBN | : |
The oxygen-to-metal atom ratio, or O/M, of solid solution uranium- plutonium oxide reactor fuel is a measure of the concentration of crystal defects in the oxide which affect many fuel properties, particularly, fuel oxygen potential. Fabrication of a high-temperature oxygen electrode, employing an electro-active tip of oxygen-deficient solid-state electrolyte, intended to confirm gaseous oxygen potentials is described. Uranium oxide and plutonium oxide O/M reference materials were prepared by in situ oxidation of high purity metals in the thermobalance. A solid solution uranium-plutonium oxide O/M reference material was prepared by alloying the uranium and plutonium metals in a yttrium oxide crucible at 1200°C and oxidizing with moist He at 250°C. The individual and solid solution oxides were isothermally equilibrated with controlled oxygen potentials between 800 and 1300°C and the equilibrated O/ M ratios calculated with corrections for impurities and buoyancy effects. Use of a reference oxygen potential of -100 kcal/mol to produce an O/M of 2.000 is confirmed by these results. However, because of the lengthy equilibration times required for all oxides, use of the O/M reference materials rather than a reference oxygen potential is recommended for O/M analysis methods calibrations. (auth).
| Author | : United States. Energy Research and Development Administration |
| Publisher | : |
| Total Pages | : 1104 |
| Release | : 1977 |
| Genre | : Medicine |
| ISBN | : |
| Author | : United States. Energy Research and Development Administration |
| Publisher | : |
| Total Pages | : 780 |
| Release | : 1976 |
| Genre | : Power resources |
| ISBN | : |
| Author | : |
| Publisher | : |
| Total Pages | : 872 |
| Release | : 1986 |
| Genre | : Power resources |
| ISBN | : |
| Author | : United States. Energy Research and Development Administration. Technical Information Center |
| Publisher | : |
| Total Pages | : 1682 |
| Release | : 1977 |
| Genre | : Force and energy |
| ISBN | : |
| Author | : |
| Publisher | : |
| Total Pages | : 260 |
| Release | : 1977 |
| Genre | : Aeronautics |
| ISBN | : |
| Author | : |
| Publisher | : |
| Total Pages | : 724 |
| Release | : 1976 |
| Genre | : Nuclear energy |
| ISBN | : |
| Author | : Masato Kato |
| Publisher | : CRC Press |
| Total Pages | : 183 |
| Release | : 2022-10-17 |
| Genre | : Science |
| ISBN | : 1000686000 |
Materials Science and Fuel Technologies of Uranium and Plutonium Mixed Oxide offers a deep understanding of MOX properties for nuclear fuels that will be useful for performance evaluation. It also reviews fuel property simulation technology and an irradiation behavior model required for performance evaluation. Based on research findings, the book investigates various physical property data in order to develop MOX fuel for sodium-cooled fast reactors. It discusses a database of MOX properties, including oxygen potential, melting temperature, the lattice parameter, sound speeds, thermal expansion, thermal diffusivity, oxygen self-diffusion, and chemical diffusion coefficients, that was used to derive a science-based model of MOX properties (Sci-M Pro) for fuel-performance code development. Features: Concisely covers the essential aspects of MOX nuclear fuels. Explores MOX nuclear fuels by systematically evaluating various physical property values using a behavior model. Presents fuel property simulation technology. Considers oxygen potential, the lattice parameter, sound speeds, and oxygen self-diffusion. Discusses melting temperature, thermal expansion, thermal diffusivity, and chemical diffusion coefficients. The book will be useful for researchers and engineers working in the field of nuclear fuels and nuclear materials.
| Author | : Dasarathi Das |
| Publisher | : Springer Science & Business Media |
| Total Pages | : 423 |
| Release | : 2013-12-24 |
| Genre | : Technology & Engineering |
| ISBN | : 1447155890 |
This book presents the state of the art on thermophysical and thermochemical properties, fabrication methodologies, irradiation behaviours, fuel reprocessing procedures, and aspects of waste management for oxide fuels in general and for thoria-based fuels in particular. The book covers all the essential features involved in the development of and working with nuclear technology. With the help of key databases, many of which were created by the authors, information is presented in the form of tables, figures, schematic diagrams and flow sheets, and photographs. This information will be useful for scientists and engineers working in the nuclear field, particularly for design and simulation, and for establishing the technology. One special feature is the inclusion of the latest information on thoria-based fuels, especially on the use of thorium in power generation, as it has less proliferation potential for nuclear weapons. Given its natural abundance, thorium offers a future alternative to uranium fuels in nuclear technology. In closing, the latest information on conventional uranium and plutonium fuels is also provided.
