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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.
David Loaiza, Rene Sanchez, David Hayes, Charlene Cappiello
Nuclear Science and Engineering | Volume 152 | Number 1 | January 2006 | Pages 65-75
Technical Paper | doi.org/10.13182/NSE06-A2564
Articles are hosted by Taylor and Francis Online.
An experiment to investigate the critical mass of 237Np was performed at the Los Alamos Critical Experiments Facility. The critical configuration consisted of a 6.07-kg neptunium sphere surrounded by 62.555 kg of highly enriched uranium hemispherical shells. The experiment was performed in order to decrease the large uncertainty in the critical mass of 237Np for criticality safety and nonproliferation issues. The critical configuration had an experimental keff of 1.003. Comparison of the experimental results with computational methods used to predict the keff of the system led to identification of a large discrepancy in the 237Np cross-section data from ENDF/B-VI used by the analysis performed with the MCNP code. In an effort to bound the uncertainty on the experimental keff, a sensitivity analysis was performed. This analysis systematically examines uncertainties associated with the critical experiment as they affect the calculated multiplication factor. The systematic analysis is separated into uncertainties due to mass measurements, uncertainties due to geometry of materials, and uncertainties due to impurities. Each type of uncertainty is analyzed individually, and a total combined uncertainty is derived. The sensitivity analysis on this experiment yielded a total combined uncertainty on the measured keff of ±0.0032.