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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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Fusion Science and Technology
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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Yuki Ishimoto, Yousuke Nakashima, Akio Sagara, Eiichi Ishinuki, Shinji Kobayashi, Masayuki Yoshikawa, Kiyoshi Yatsu
Fusion Science and Technology | Volume 39 | Number 1 | January 2001 | Pages 249-252
Poster Presentations | doi.org/10.13182/FST01-A11963453
Articles are hosted by Taylor and Francis Online.
In this paper, operational methods of carbon sheet pump (CSP) which aims at control of hydrogen recycling are investigated. Although the pumping effect of CSP is confirmed in an actual plasma device, the experimental results suggest that a certain amount of gases are adsorbed on CSP under an actual plasma circumstance. The operational methods are contrived and are carried out for the reduction of the adsorbed gases on CSP. Time evolution of total pressures in several regions of the GAMMA 10 vacuum vessel is estimated by numerical analysis in order to evaluate the feasibility of applying CSP to the GAMMA 10 central region. These results suggest that CSP is applicable to actual plasma devices under a suitable operational method.