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Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
R. L. Ritzman, A. J. Markworth, W. Oldfield, W. Chubb
Nuclear Technology | Volume 9 | Number 2 | August 1970 | Pages 167-187
Fuel Performance Model | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28806
Articles are hosted by Taylor and Francis Online.
The swelling of the refractory nuclear fuels, UO2, UN, and UC, at temperatures of the order of 1700°C, is related to the behavior of the fission gases as these gases make their way out of the fuels. In all three fuels, the fission gases first precipitate to form a two-phase system consisting of solid fuel and gaseous precipitates. These precipitates or bubbles grow in-reactor mainly by the accretion of new fission gas atoms. New gas atoms diffuse to the older bubbles (which are formed in the first few minutes of irradiation) causing these bubbles to grow and to swell the fuel. In UC, this process continues with very little change to produce rather large amounts of swelling. However, at about 10 vol% swelling of UC, bubbles begin to overlap to form channels and gas release begins to accelerate. In UN and UO2 at about 1700°C, UN and UO2 vapors begin to migrate across the growing bubbles as a result of the temperature gradients usually found in fuels in-reactor. This process, which is a form of zone refining, results in rapid and efficient gas collection and release. This gas release may reduce the stresses applied by UN and UO2 to their claddings; but the zone refining process does not completely eliminate swelling stresses because swelling precedes gas release. Also, the zone refining or “restructuring” process tends to eliminate built-in porosity; so that while built-in porosity is very effective in limiting the swelling of UC, such porosity is relatively ineffective in reducing the swelling of UN and UO2 at temperatures where restructuring is rapid. These processes are described in terms of classical chemical and physical metallurgical models; and the validity of the models is illustrated, although not necessarily proved, by the results of high-temperature irradiation experiments.