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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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
Fusion Science and Technology
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.
W. H. Olson, W. E. Ruther
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 318-322
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32333
Articles are hosted by Taylor and Francis Online.
Carbon has been shown to be an effective getter for cesium in liquid sodium. A cesium trap containing reticulated vitreous carbon and operating at 190°C has been used at the Experimental Breeder Reactor II to reduce fission product cesium activity in the primary sodium coolant from a maximum of 15 kBq/g to ∼870 Bq/g.
