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Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
Meeting Spotlight
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
NRC issues interim guidance on reactor component disposal
The Nuclear Regulatory Commission is providing guidance to nuclear power plant licensees looking to use decommissioning trust fund (DTF) money to dispose of major reactor components like steam generators and reactor vessel heads while the plant is still operational.
On August 5, the NRC issued the interim staff guidance Use of the Decommissioning Trust Fund During Operations for Major Radioactive Component Disposal (REFS-ISG-2024-01), which provides the NRC staff’s regulatory position regarding the use a reactor’s DTF for the disposal of major radioactive components while the plant is still operational. Under NRC regulations, the DTF may be accessed solely for decommissioning expenses as defined in 10 CFR 50.2, unless an exemption is granted by the NRC.
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.