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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
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.
M. Bober, H. Kleykamp, G. Schumacher
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 172-182
Technical Paper | Fuel | doi.org/10.13182/NT75-A24416
Articles are hosted by Taylor and Francis Online.
Redistribution of plutonium has been examined in three hypo stoichiometric mixed oxide fuel pins irradiated in the fast flux of the RAPSODIE reactor. From the results of these examinations, the effective heat of transport of thermal diffusion of plutonium is estimated. The increase in central temperature is determined with plutonium distributions calculated from thermal diffusion and estimated from postirradiation examinations, respectively. In stoichiometric fuels, a temperature increase of up to 150°C must be anticipated due to plutonium enrichment by evaporation-condensation processes, while in strongly hypostoichiometric fuels the increase in central temperature, caused in this case by thermal diffusion, does not exceed 50°C for power ratings below 450 W/cm. The radial variation of the O/(U +Pu) ratio is calculated since it strongly influences the vapor pressures of the fuel component species and therefore influences the redistribution by evaporation-condensation processes.
