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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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Latest News
Perpetual Atomics, QSA Global produce Am fuel for nuclear space power
U.K.-based Perpetual Atomics and U.S.-based QSA Global claim to have achieved a major step forward in processing americium dioxide to fuel radioisotope power systems used in space missions. Using an industrially scalable process, the companies said they have turned americium into stable, large-scale ceramic pellets that can be directly integrated into sealed sources for radioisotope power systems, including radioisotope heater units (RHUs) and radioisotope thermoelectric generators (RTGs).
D. A. Niebruegge, E. L. Tolman, C. W. Solbrig
Nuclear Science and Engineering | Volume 68 | Number 3 | December 1978 | Pages 363-368
Technical Note | doi.org/10.13182/NSE78-A27316
Articles are hosted by Taylor and Francis Online.
Thus far, existing computer programs have been adequate to predict the behavior of the loss-of-fluid test facility (LOFT) non-nuclear loss-of-coolant experiments. The work presented here describes a predictive capability for modeling nuclear experiments to determine if the same fuel can be used in several experiments. This is analogous to determining if fuel may be reused after a pressurized water reactor loss-of-coolant accident. We are concerned here with discussing only best-estimate calculations for experimental predictions and not the conservative models used for licensing. It was found that an adequate analysis procedure could be established by modeling accurately the fuel stored energy before the experiment is initiated. The initial stored energy in the fuel was found to be the most important fuel rod parameter influencing the maximum cladding temperature obtained in the transient.