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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
Latest Magazine Issues
Jul 2024
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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.
Carleton D. Bingham, Morris W. Lerner
Nuclear Technology | Volume 23 | Number 2 | August 1974 | Pages 106-111
Technical Paper | Nuclear Safeguards (Presented at November 1973 Meeting) / Safeguard | doi.org/10.13182/NT74-A31442
Articles are hosted by Taylor and Francis Online.
Nuclear materials safeguards have spurred the development of faster, cheaper, and more reliable methods for the assay of uranium materials in the nuclear fuel cycle. These requirements have been met by an elegantly simple method suitable for both manual and automated operation. Dissolution of some samples remains a vexing problem, but some advances in this area are being made. Intra-and interlaboratory control programs are necessary to maintain the highest possible reliability of the analytical results.