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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
Keith V. Davidson
Nuclear Technology | Volume 28 | Number 1 | January 1976 | Pages 23-30
Technical Paper | Fuels for Pulsed Reactor / Fuel | doi.org/10.13182/NT76-A31536
Articles are hosted by Taylor and Francis Online.
Improved test facilities are required for safety studies of liquid-metal fast breeder reactor (LMFBR) fuel bundles. The objectives for such a test facility can be obtained by installing a converter section in the central region of the Transient Reactor Test Facility (TREAT) core to provide a hardened neutron spectrum around the test section containing the large cluster of LMFBR fuel pins. The expertise gained at Los Alamos Scientific Laboratory in the Rover fuel element development program was extended to fabricate (U,Zr)C-graphite composite fuel rods for scoping studies of candidate fuels. Selected properties determined for the carbide-graphite composite fuel rods provided for the first scoping test indicate that they are definitely a candidate fuel for a TREAT converter.
