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
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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!
Latest Magazine Issues
Apr 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.
