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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
John R. White, Thomas F. DeLorey
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 129-147
Technical Paper | Fission Reactor | doi.org/10.13182/NT91-A34551
Articles are hosted by Taylor and Francis Online.
A detailed sensitivity and uncertainty analysis is performed for several parameters of interest in the design of the high-conversion reactor (HCR) concept. The main goals of this work are to determine the response standard deviation due to basic nuclear data uncertainties and to incorporate integral experiment information from the PROTEUS facility to reduce the computed uncertainties, where possible. The results for reactivity and five important reaction rate ratios (at the 0% void state) that are part of the measurement program in the PROTEUS phase II experiments are highlighted. In addition, the void coefficient at both low void and high void is studied. The computed correlation coefficients between the PROTEUS and HCR models are uniformly high for all responses. This indicates that a reduction in uncertainty can be achieved within the measurement uncertainty and that the PROTEUS experiments were ideal for the physics characterization of HCR responses.