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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
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.
D. C. Witt, R. F. Bradley
Nuclear Technology | Volume 43 | Number 2 | April 1979 | Pages 244-258
Technical Paper | The Back End of the Light Water Reactor Fuel Cycle / Fuel Cycle | doi.org/10.13182/NT79-A16315
Articles are hosted by Taylor and Francis Online.
One alternative for closing the nuclear fuel cycle is efficient, high decontamination separation of uranium and plutonium and fabrication of a Pu-U mixed-oxide fuel Detailed flowsheets were prepared by Savannah River Laboratory for a conceptual 10 MT/day reprocessing facility. The generation of liquid waste and the associated liquid waste handling facilities for the reprocessing plant were defined. Over 40 individual waste streams were identified. The reference facility generates 6.4 m3 (1700 gal) of high-level liquid waste (HLLW) per day, which is converted to 0.5 m3 (130 gal) of glass contained in three packages, each 0.3 m (12 in.) in diameter × 3 m (10 ft) high. Each operating day, the process converts 2.9 m3 (775 gal) of concentrated intermediate-level liquid waste (ILLW) to 4 m3 (1050 gal) of cemented solid in 21 carbon steel drums. Large-scale underground tank storage of liquid waste is eliminated by prompt solidification of the HLLW and ILLW. Each container of glass contains 30 kW nuclear decay heat and must be stored in water for an interim period prior to shipment to a federal repository.
