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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Virginia utility considers SMRs
Dominion Energy Virginia has issued a request for proposals from leading nuclear companies to study the feasibility of putting a small modular reactor at its North Anna nuclear power plant.
While the utility says it is not a commitment to build an SMR at the site, the RFP is “an important first step in evaluating the technology and the North Anna site to support Dominion Energy customers’ future energy needs consistent with the company’s most recent Integrated Resource Plan.”
P. Deramaix, D. Haas, J. Van De Velde
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 47-53
Technical Paper | Mixed-Oxide Fuel / Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34801
Articles are hosted by Taylor and Francis Online.
The mixed-oxide (MOX) fuel of the current generation (MIMAS) is confronted with the challenge of reaching the same quality and reliability as UO2 fuel, while the related data base accumulated so far is still limited. Its in-reactor behavior, therefore, has been assessed based on the lessons from previous generations of MOX fuel. Results are presented for attributes specific to the MOX nature of the fuel, irrespective of the specific fuel design features. The results obtained progressively with MIMAS fuel confirm the adequacy of such an assessment.