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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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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.
Masabumi Nishikawa
Fusion Science and Technology | Volume 59 | Number 2 | February 2011 | Pages 350-362
Technical Paper | doi.org/10.13182/FST11-A11651
Articles are hosted by Taylor and Francis Online.
The tritium balance in a D-T fusion power reactor to assure a self-sustainable tritium system is discussed in this paper, comparing the amount of tritium consumed in the fueling cycle including the plasma vessel with the amount of tritium generated in the blanket system. It is determined that recovering tritium from the redeposition layer is highly effective in achieving tritium balance. It is also known from this discussion that having a burning plasma with an overall burning efficiency >0.5% is needed to maintain tritium balance. A burning efficiency >3 to 4% is even better because the tritium balance increases. It is also known that a first-wall material having an overall trapping factor >0.005 or that having an overall permeation loss ratio >0.0001 is not desirable because the tritium loss at the plasma vessel becomes too large to maintain the tritium balance. This discussion also finds that a blanket system with an overall breeding ratio of [approximately]1.1 is desirable early in fusion development to maintain a short tritium doubling time.