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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
Leslie Cave, William E. Kastenberg
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 29-42
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33708
Articles are hosted by Taylor and Francis Online.
The development and application of two quantitative methods that could be used as part of the decisionmaking process in the licensing of nuclear power plants are described. These methods are (a) the use of quantitative screening criteria to assess the adequacy of the safety functions in existing plants and (b) the use of value/impact or cost /benefit analysis to determine limits to the cost-effective expenditure on“back-fitting” to improve safety. It also is shown that the results obtained by the two methods are not necessarily compatible with one another. As an example, the two methods are applied to the question of improving the decay heat removal function for light water reactors. Screening criteria are presented for this function for both pressurized water reactors and boiling water reactors. The value/impact assessment is carried out as a function of site population, existing plant features, and new plant features.