ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
Mitchel E. Cunningham, Donald D. Lanning
Nuclear Technology | Volume 60 | Number 3 | March 1983 | Pages 420-429
Technical Paper | LWR Control Materials—I and II / Nuclear Fuel | doi.org/10.13182/NT83-A33128
Articles are hosted by Taylor and Francis Online.
Irradiation data collected from test fuel rods that were identically built and operated may be used to define a range of normal performance for a specific fuel rod design. By comparing the data to computer code calculations, it is possible to define the range of applicability of fuel thermal performance computer codes. Data scatter for the centerline temperature from identical rods in several test assemblies decreases from the first power ascension to the third power ascension. Calculated uncertainty bands for the data (i.e., expected variability for the data assuming dimensional tolerances, material property uncertainties, and power uncertainties) are found to be larger than the data scatter. The FRAPCON-2 temperature calculations agree with temperature data from helium-filled rods; however, the code does not match beginning-of-life temperatures from a xenon-filled rod. However, the code results agreed with data obtained from the xenon-filled rod at higher burnup, thus indicating that the code adequately calculates fuel temperatures for fission gas-filled rods later in life.