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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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.
M. N. Özişik, M. D. Silverman
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 240-246
Technical Paper | Fuel | doi.org/10.13182/NT72-A31113
Articles are hosted by Taylor and Francis Online.
High temperature gas-cooled reactors (HTGRs) employ fuel elements which are separated from the coolant stream by graphite. Pressure differentials induced by turbulent flow along the coolant channel length of the fuel assembly can cause transverse flow of the gas through the graphite sleeve. Such transverse flow could transfer fission products from broken fuel particles into the main coolant stream. Mathematical analysis shows that the thickness of the annular gap between the fuel element and the graphite sleeve is an important factor that controls fission product transport by this mechanism. The data obtained from experiments performed in a high temperature, pressurized helium loop correlate satisfactorily with this analysis, and an estimate of cesium release to the coolant via this mechanism has been made for the Fort St. Vrain reactor.