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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
William E. Vesely, Thomas C. Davis
Nuclear Technology | Volume 68 | Number 2 | February 1985 | Pages 226-234
Technical Paper | Fabrication of Components of the Creys-Malville Plant / Nuclear Safety | doi.org/10.13182/NT85-A33555
Articles are hosted by Taylor and Francis Online.
Risk importance measures are developed to quantify the worths of design features and human actions in both controlling and reducing risk. The quantification of worths can be used to help focus and prioritize efforts in backfitting programs, reliability assurance programs, inspection programs, and general risk management programs. The risk importance measures described are straightforward mathematically and have a natural physical interpretation. As a demonstration of their utility, the measures are applied to the probabilistic risk analyses (PRA) performed in the U.S. Nuclear Regulatory Commission Reactor Safety Study Methodology Applications Program. The results greatly enhance the information provided by the PRA and show extremely interesting behaviors. Within a plant and across plants, worths vary by orders of magnitude. Systems, components, and human actions that are important in reducing risk are not necessarily those that are important in controlling or assuring risk. The worths are graphically portrayed to more effectively communicate the messages to managers and decisionmakers. The applications indicate that the described importance evaluations should be an intimate part of any PRA.