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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Federal court finds in favor of Diablo Canyon license review
A review from the Ninth Circuit Court of Appeals this week denied a challenge to the Diablo Canyon nuclear plant’s license renewal application extension granted by the federal government.
In late 2023, the Nuclear Regulatory Commission agreed to formally docket the California plant’s request to extend plant operations beyond the current license expiration dates of 2024 and 2025 for the two respective units.
A. E. Ruggles, A. D. Vasil’ev, N. W. Brown, M. W. Wendel
Nuclear Science and Engineering | Volume 125 | Number 1 | January 1997 | Pages 75-83
Technical Paper | doi.org/10.13182/NSE97-A24255
Articles are hosted by Taylor and Francis Online.
Analytical and numerical investigations of critical heat flux (CHF) and reactor thermal limits are conducted for oscillatory two-phase flows often associated with natural circulation conditions. The CHF and associated thermal limits depend on the amplitude of the flow oscillations, the period of the flow oscillations, and the thermal properties and dimensions of the heater. The value of the thermal limit can be much lower in unsteady flow situations than would be expected using time average flow conditions. The properties of the heater strongly influence the thermal limit value in unsteady flow situations, which is very important to the design of experiments to evaluate thermal limits for reactor fuel systems.