ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
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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August 2024
Nuclear Technology
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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
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.