ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Operations & Power
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.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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April 2024
Nuclear Technology
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February 2024
Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
Andrej Prosek, Borut Mavko
Nuclear Technology | Volume 158 | Number 1 | April 2007 | Pages 69-79
Technical Note | Best Estimate Methods | doi.org/10.13182/NT07-1
Articles are hosted by Taylor and Francis Online.
The approval of the revised rule on the acceptance of emergency core cooling system performance in 1988 triggered a significant interest in the development of codes and methodologies for uncertainty evaluation of best-estimate loss-of-coolant accident (LOCA) analyses. The code scaling, applicability, and uncertainty evaluation method was developed and demonstrated for a large-break LOCA in a pressurized water reactor. Later, several new best-estimate plus uncertainty methods (BEPUs) were developed around the world. The purpose of this paper is to identify and compare the statistical approaches of BEPU methods and present their importance for licensing applications in nuclear power plants. The study showed that the uncertainty analysis with random sampling of input parameters, using the nonparametric statistical tolerance limits for estimating uncertainty of output parameters, is the commonly accepted approach today. The existing BEPU methods seem mature enough, while the future research may be focused on the codes with internal assessment of uncertainty.