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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
H. B. Choi, T. J. Downar
Nuclear Science and Engineering | Volume 111 | Number 2 | June 1992 | Pages 205-213
Technical Note | doi.org/10.13182/NSE92-A23934
Articles are hosted by Taylor and Francis Online.
Depletion perturbation theory has been extended to the closed nuclear fuel cycle, and methods have been developed for computing the constrained sensitivities that account for fuel reprocessing and fabrication. An iterative method was developed to solve the sensitivity equations and applied to the closed fuel cycle of the Integral Fast Reactor (IFR). The sensitivities computed using the method were in good agreement with sensitivities from direct subtraction of perturbed and unperturbed depletion calculations. The closed fuel cycle sensitivities were also compared with the sensitivities for the open fuel cycle without reprocessing. The closed fuel cycle sensitivities were found to be larger, particularly for isotopes higher up the burnup chain. These results indicate this work would have particular importance for the analysis of advanced reactor designs with closed fuel cycles, such as the IFR. The methods developed here will facilitate accurate and efficient sensitivity studies of such reactors.