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
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
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.
John E. Mendel
Nuclear Technology | Volume 32 | Number 1 | January 1977 | Pages 72-87
Technical Paper | Materials in Waste Storage / Radioactive Waste | doi.org/10.13182/NT77-A31739
Articles are hosted by Taylor and Francis Online.
Glass is a good material in which to incorporate high-level radioactive waste (HLW) for permanent storage. HLW, a complex mixture of fission products and actinides, results from the reprocessing of spent power reactor fuel elements to reclaim uranium and plutonium. Processes for making low-temperature waste glasses (1050°C processing temperature) have been developed to the stage that they can be utilized in commercial reprocessing plants in the early 1980’s. A representative low-melting waste glass formulation has been shown, in accelerated tests, to possess satisfactory thermal and radiation stability for many centuries of storage, and indications are that this stability will be maintained for longer times. The waste glass can be melted and stored in Type 304L stainless-steel canisters, although investigations of metals that may have increased high-temperature strength is continuing. A ceramic melting process that will permit manufacture of higher melting HLW glass, if this proves desirable, is also being developed.