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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
Meeting Spotlight
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
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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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.
Takanobu Kamei, Tadashi Yoshida, Toshikazu Takeda, Takuya Umano
Nuclear Science and Engineering | Volume 91 | Number 1 | September 1985 | Pages 11-33
Technical Paper | doi.org/10.13182/NSE85-A17126
Articles are hosted by Taylor and Francis Online.
The prediction accuracy of the burnup characteristics of large liquid-metal fast breeder reactors (LMFBRs) is very hard to evaluate because of the unavailability of the direct experimental information. A quantitative evaluation was performed on the accuracy of the burnup property by use of the sensitivity coefficients in a large LMFBR and the covariance matrix of nuclear data. Also evaluated was the decrease in prediction error when the cross-section set was adjusted by the use of experimental data, such as criticality, reaction rate ratios, and others. It was concluded that accuracy with the direct use of current nuclear data is ±30% for burnup reactivity loss and ±5% for breeding ratio. On the other hand, the accuracy would be improved to ±18% and ±2.5% by utilizing the experimental data obtained on the zero-power plutonium reactor assembly.