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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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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Take steps on SNF and HLW disposal
Matt Bowen
With a new administration and Congress, it is time once again to ponder what will happen—if anything—on U.S. spent nuclear fuel and high-level waste management policy over the next few years. One element of the forthcoming discussion seems clear: The executive and legislative branches are eager to talk about recycling commercial SNF. Whatever the merits of doing so, it does not obviate the need for one or more facilities for disposal of remaining long-lived radionuclides. For that reason, making progress on U.S. disposal capabilities remains urgent, lest the associated radionuclide inventories simply be left for future generations to deal with.
In March, Rick Perry, who was secretary of energy during President Trump’s first administration, observed that during his tenure at the Department of Energy it became clear to him that any plan to move SNF “required some practical consent of the receiving state and local community.”1
Masatoshi Yamasaki, Hironobu Unesaki, Akio Yamamoto, Toshikazu Takeda, Masaaki Mori
Nuclear Technology | Volume 180 | Number 1 | October 2012 | Pages 18-27
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT12-A14516
Articles are hosted by Taylor and Francis Online.
The use of highly-enriched fuels is an effective method for reducing the number of spent fuel assemblies and improving fuel cycle economics, e.g., with >5 wt% 235U. However, from a criticality safety point of view, such high enrichment levels require a significant investment for the considerable modification of most facilities and equipment. Erbia-credit super-high-burnup fuel offers an effective solution that can solve the problem: Small amounts of erbia added to the entire amount of UO2 powder can reduce the reactivity level to less than that observed at a 5 wt% enrichment level, thus eliminating the need for the modifications mentioned above. A series of criticality safety analyses has been performed to determine the minimum and sufficient content of erbia that can guarantee a suitable erbia credit. As a noteworthy result, the erbia content required was determined for corresponding values of uranium enrichment in a range >5 wt%, as indicated in our ECOS (Erbia COntent for Sub-criticality judgment) diagram. This paper outlines a series of criticality safety analyses and explains how the minimum erbia content can be determined to ensure subcriticality for a >5 wt% enrichment fuel to ensure that the fuel obtained is equivalent to that whose enrichment is <5 wt%.