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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.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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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Remembering Joseph M. Hendrie
Joseph M. Hendrie
To those of us who knew Joe, even prior to his appointment as chair of the Nuclear Regulatory Commission, it is an understatement to say that he was a larger-than-life member of the nuclear science and technology enterprise. He was best known to the broader community for two major accomplishments: the design and construction of the High Flux Beam Reactor (HFBR) at Brookhaven National Laboratory and the creation of the standard review plan (SRP) for the U.S. Atomic Energy Commission.
In addition to the products of these endeavors becoming major fundaments to their respective communities, they were uniquely Joe. The safety analysis report for the HFBR was written essentially single-handedly by him. This was true of the SRP as well, which became the key safety review document for the NRC as it performed safety reviews for the growing number of power reactor applications in the United States. His deep technical knowledge of nuclear engineering and his extraordinary management skills made this possible.
Hiroyuki Sato, Xing L. Yan, Yukio Tachibana, Kazuhiko Kunitomi, Yukitaka Kato
Nuclear Technology | Volume 185 | Number 3 | March 2014 | Pages 227-238
Technical Paper | Fission Reactors | doi.org/10.13182/NT13-97
Articles are hosted by Taylor and Francis Online.
The transient response of the high-temperature gas-cooled reactor (HTGR) to depressurized loss of forced circulation combined with failure of all reactor trip systems, a beyond-design-basis accident, is analyzed for an extended period of time during which no active core cooling is resumed. The characteristic behavior of the reactor during the long-term conduction cooldown event is found to be shaped by several parameters that are usually not considered in the safety design of the HTGR. For example, while the Doppler effect is usually relied upon to provide inherent shutdown of the reactor, the reactivity coefficient of temperature of the graphite moderator is found to be a critical parameter for determining the final settling temperature of the fuel following the recriticality. Furthermore, this study finds that the peak fuel temperature reached during this event is correlated strongly even to the initial core operating temperature prior to the initiation of the transient event. These and other results of this study are expected to provide useful input to the development of enhanced safety design guidelines for commercial HTGRs in the aftermath of the Fukushima accident.