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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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.”
Hans-Werner Wiese
Nuclear Technology | Volume 102 | Number 1 | April 1993 | Pages 68-80
Technical Paper | Mixed-Oxide Fuel / Nuclear Fuel Cycle | doi.org/10.13182/NT93-A34803
Articles are hosted by Taylor and Francis Online.
Based on the use of the Joint Evaluated File (JEF-1) with the KARBUS burnup code system and subsequent KORIGEN code calculations, the characteristics of spent pressurized water reactor mixed-oxide (MOX) fuels are analyzed. Actinide masses, decay heat, radioactivities, and radiation are discussed for burnups of 40 to 55 GWd/tonne HM for MOX fuels based on natural uranium and on uranium tailings. Multiple plutonium recycling is considered at a burnup of 50 GWd/tonne HM. The results are compared with earlier data at a burnup of 33 GWd/tonne HM. The high-exposure MOX fuels are found to contain large amounts of the heat-releasing and radiating nuclides, 238Pu and 244Cm. The 238Pu in the plutonium, which is to be used for the fabrication of fuel elements from recycled MOX, requires special shielding or a change from glove box techniques to an automated treatment.