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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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.
Challenge: Expedite licensing and deployment of advanced reactor designs.
How: Expedite the development and deployment of advanced reactor concepts by developing a practical path forward for applying innovative approaches to licensing inventive advanced reactor designs that reduces the regulatory burden while still ensuring safety. The regulatory system needs to meet the pace of commerce.
Background: Eliminating the difficulties facing the licensing and construction of new nuclear power plants would bring great benefits. These issues are associated with both evolutionary reactor construction as well as the construction of advanced reactor concepts. Other industries, such as the transportation or pharmaceutical industries, have achieved what appears to be a better balance between allowing for growth and innovation while maintaining safety standards. In the early years, nuclear power plant construction was done quickly, and if it could be done so again this could have a major impact on the feasibility, attractiveness, and profitability of a project. Additionally, siting and supply chain and vendor interactions can be some of the most expensive and potentially time-intensive aspects of a construction project. Without improvement, future nuclear power plant construction will remain unattractive as an investment.
Institutional difficulties associated with obtaining design certification for novel reactor technologies could be avoided by first constructing and operating a prototype plant that has sufficient extra margin and safety features to justify near-term Nuclear Regulatory Commission (NRC) approval for prototype construction and testing. This process is explicitly contemplated in 10 CFR 50.43 e(2), but is seldom or never used. Such a process could be carried out with the expectation that the results of testing and operation of a prototype plant would support subsequent expeditious certification of a viable commercial (as opposed to prototype) design.
The default path of direct design certification for a commercial design by analysis and scaled-down test facilities has proven to be extremely lengthy, even for Generation 2 plants, for which Part 50 safety requirements already exist. For other technologies lacking a current Part 50 equivalent, design certification within the traditional paradigm looks even more difficult. The proposed license-by-prototype approach would be loosely analogous to the lead test assembly approaches now used for new Light Water Reactor (LWR) fuel designs.
Data emerging from special surveillance and testing performed over many years in the first reactor module or modules would support the safety case for all subsequent reactor modules. Safety analysis for early testing in the lead reactor modules would credit the larger safety margins that exist during early operation.
Last modified May 12, 2017, 1:23am CDT