ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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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Nuclear Science and Engineering
August 2024
Nuclear Technology
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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.
P. Grillo, G. Testa
Nuclear Technology | Volume 5 | Number 3 | September 1968 | Pages 130-139
Technical Paper and Note | doi.org/10.13182/NT68-A28042
Articles are hosted by Taylor and Francis Online.
Hot spot factors due to fissile material segregation in UO2-PuO2 fuels and to geometrical tolerances in the fuel rods are calculated for both vibrationally compacted and pelleted fuels to produce optimum design for light-water reactors. Neutron flux distribution in the fuel is calculated using the transport theory, while the trend of the heat flux transferred to the coolant is evaluated by a three-dimensional heat-transfer code. Segregation of fissile material is significant for vibrationally compacted fuel, and appears negligible for pelleted fuel. The geometrical tolerances considered give values for engineering hot channel factors that are quite relevant for fuel-rod design.
