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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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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.
J. A. Vitti, P. K. Doherty, G. F. di Lauro, J. C. Gilbertson, D. W. Stuteville
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 442-451
Technical Paper | Fuel | doi.org/10.13182/NT75-A24444
Articles are hosted by Taylor and Francis Online.
A preliminary assessment of proof testing 13 prototypical liquid-metal fast breeder reactor (LMFBR) carbide fuel assemblies in fast test reactor (FTR) driver positions leads to the conclusion that the testing plan is practical and should produce a large amount of data at operating conditions very similar to those that would be found in large commercial carbide-fueled LMFBR s. Three subassembly configurations were designed, each capable of being directly substituted into FTR driver positions and made compatible with the FTR geometry, fuel handling, power, temperature, subassembly flow rates, and pin-bundle pressure drop. Two sodium-bonded designs, one with 91 fuel pins with a 0.370-in. o.d. and the other with 127 fuel pins with a 0.315-in. o.d. per subassembly were established. Calculated peak linear power and peak discharge burnup slightly exceed present commercial design objectives of 30 kW/ft and 73 MWd/kg. Individual assembly power history, flux, and enrichments are represented quite well in the FTR for commercial outer-zone fuel assemblies. Inner-zone operating conditions, however, are not simulated as closely. Impact effects of the proof-test assemblies on FTR operation are judged to be manageable.