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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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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Latest News
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
Sergey I. Belousov, Krassimira D. Ilieva
Nuclear Science and Engineering | Volume 126 | Number 2 | June 1997 | Pages 239-244
Technical Paper | doi.org/10.13182/NSE97-A24477
Articles are hosted by Taylor and Francis Online.
A new adjoint synthesis (ASYNT) method is proposed for synthesizing a three-dimensional solution from two- and one-dimensional solutions of the adjoint neutron transport equation. Its correctness and fast run ability are appropriate for evaluating neutron irradiation for the VVER/pressurized water reactor pressure vessel—especially for surveillance sites located out of the reactor core midplane.The solution axial dependence in circular cylindrical geometry is the main approximation used. The ASYNT method could be reduced to the traditional synthesis method by some supplementary approximations. The solution for every type of reactor is obtained by calculating the adjoint neutron transport equation only once for each surveillance site.
