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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.
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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.
Ned E. Bibler
Nuclear Technology | Volume 34 | Number 3 | August 1977 | Pages 412-415
Technical Paper | Chemical Processing | doi.org/10.13182/NT77-A31805
Articles are hosted by Taylor and Francis Online.
The radiolytic oxidation of Fe(II) and the destruction of sulfamic acid (SA) in feed solutions for solvent extraction purification of 237Np and 238Pu from spent nuclear fuels have been investigated. Cobalt-60 gamma radiolysis of simulated solutions established that 100-eV yields for depletion of Fe(II) and SA are 13 and 5.6, respectively. Also, the normally occurring components of process solutions do not significantly affect these yields. An actual process solution was studied in which radiolysis was almost entirely from gamma-ray and beta-particle decay of 235U fission products along with a small fraction from alpha-particle decay of transuranium isotopes. In this solution, G(Fe3+) is 12, which is in good agreement with results with simulated solutions. Interpretation of the results suggests that Fe(II) not only reduces Np(V) and Pu(IV) but also protects the reduced states from reoxidation by radiolytically formed intermediates; when Fe(II) is depleted, the reduced states are immediately oxidized.