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Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
Eberhard Teuchert, Hans Joachim Rütten, Heinz Werner
Nuclear Technology | Volume 38 | Number 3 | May 1978 | Pages 374-383
Technical Paper | Fuel Cycle | doi.org/10.13182/NT78-A32035
Articles are hosted by Taylor and Francis Online.
For the pebble-bed high-temperature reactor, a wide choice is available for the design of the fuel elements and for the reactor fueling scheme. This flexibility has been utilized for the conception of different possibilities for the closure of the thorium fuel cycle. The easiest scheme is mixed-oxide recycling with repeated recycling of 236U. Loading recycle fuel into separate elements without thorium reduces the uranium ore demand by 13%. Entire separation of the feed and breed circuits brings another reduction of 5%. Furthermore, the feed-breed cycle allows the production of 233U for the near-breeder variant. This variant achieves a conversion ratio of 0.97, and it represents a possible choice for efficient protection of uranium ore resources. Within the span of uncertainties in the cost assumptions, fuel cycle costs are found to be comparable for all considered cycles, including the near-breeder.