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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
DOE extends Centrus’s HALEU production contract by one year
Centrus Energy has announced that it has secured a contract extension from the Department of Energy to continue—for one year—its ongoing high-assay low-enriched uranium (HALEU) production at the American Centrifuge Plant in Piketon, Ohio, at an annual rate of 900 kilograms of HALEU UF6. According to Centrus, the extension is valued at about $110 million through June 30, 2026.
J. M. Ryskamp, D. R. Harris, M. Becker
Nuclear Science and Engineering | Volume 77 | Number 3 | March 1981 | Pages 285-296
Technical Paper | doi.org/10.13182/NSE81-A19839
Articles are hosted by Taylor and Francis Online.
The sensitivity of light water reactor (LWR) fuel cycle parameters and costs to uncertainties in thermal nuclear data and methods is examined using a code package developed at Rensselaer Polytechnic Institute. Cross sections averaged over the thermal energy (<1- or 2-eV) group are shown to have an important economic role for LWRs. When it has been determined that fuel cycle parameters and costs are sensitive to a specific thermal group cross section, it becomes desirable to determine how specific energy-dependent cross sections influence fuel cycle parameters and costs. The FASTT code was written to compute detailed sensitivity coefficients using either a direct or a perturbation technique. Multigroup cross-section sensitivity coefficients vary with fuel exposure. After computing the changed exposure-dependent thermal group cross section, new fuel cycle parameters and costs are computed by a sequence of fuel depletion, core analysis, and cost codes. One can therefore obtain the change in fuel cycle cost for different fuel cycle options induced by a change in the shape of a detailed thermal cross section. A striking feature of our thermal analyses is the (usually) overwhelming importance of the hardened Maxwellian energy region (0.01 to 0.1 eV). The FASTT code is also used to determine the importance of the frequency distribution used to compute neutron scattering kernels based on the incoherent approximation. The sensitivities to Nelkin's scattering data are not large. A method, having potentially large implications for LWR design, is developed for obtaining correspondence among different scattering kernels.