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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
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.
Robert J. Campana
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 185-193
Technical Paper | Fuel | doi.org/10.13182/NT71-A31026
Articles are hosted by Taylor and Francis Online.
A system has been designed for the gas-cooled fast breeder reactor (GCFR) which equalizes the pressure within the fuel rods with the coolant pressure (85 atm of He) in order to eliminate the possibility of creep collapse of the fuel rods. Additional advantages that result from this design are a shortened core, relaxation of cladding tolerances, low coolant circuit activity, capability of identifying and monitoring leaking fuel elements, safer fuel handling and transport, and potential performance improvements. The system employs in-core charcoal fission-product traps and permits reactor operation with leaking fuel elements. A capsule test of the concept in the ORR has been made and results to date indicate that pressure-equalized fuel is practical and will reduce the development required for the GCFR.
