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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
College students help develop waste-measuring device at Hanford
A partnership between Washington River Protection Solutions (WRPS) and Washington State University has resulted in the development of a device to measure radioactive and chemical tank waste at the Hanford Site. WRPS is the contractor at Hanford for the Department of Energy’s Office of Environmental Management.
R.A. Langley
Fusion Science and Technology | Volume 27 | Number 2 | March 1995 | Pages 41-47
doi.org/10.13182/FST95-A11963803
Articles are hosted by Taylor and Francis Online.
The IAEA has proposed a coordinated research program to address tritium retention and release in fusion reactor plasma facing components. This program will address materials which are mainly of interest to the design and construction of ITER, namely beryllium, carbon based materials and medium and high-Z metals, e.g. tungsten, vanadium and molybdenum, but will not be limited to these materials. Experimental data are needed for: recycling models, tritium inventory estimates, tritium permeation calculations and hydrogen embrittlement characterization. The ultimate use of the data would be to influence the formation of models for use by fusion reactor designers. Judicious material choices must be made by the designers and accurate predictive codes are required in order to make these choices. The proposed coordinated research program will provide a forum for discussions between experimentalists, theoreticians, modelers and reactor designers, provide financial support for relevant research projects and collect and evaluate experimental and theoretical data. This paper briefly reviews existing data, addresses the data gaps and points out experiments designed to obtain the needed data.