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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Norway’s Halden reactor takes first step toward decommissioning
The government of Norway has granted the transfer of the Halden research reactor from the Institute for Energy Technology (IFE) to the state agency Norwegian Nuclear Decommissioning (NND). The 25-MWt Halden boiling water reactor operated from 1958 to 2018 and was used in the research of nuclear fuel, reactor internals, plant procedures and monitoring, and human factors.
Hyoung Kyu Cho, Yun Je Cho, Moon Oh Kim, Goon Cherl Park
Nuclear Technology | Volume 159 | Number 1 | July 2007 | Pages 39-58
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT07-A3855
Articles are hosted by Taylor and Francis Online.
In this study, a new concept in reactor cavity cooling systems (RCCSs) for high-temperature gas-cooled reactors (HTGRs) is proposed. The proposed RCCS consists of both water pools and active air-cooling systems, in order to overcome the disadvantages of the weak cooling capability of the air-cooled RCCS and the complex cavity structures of the water-cooled RCCS. The cooling capability of the RCCS during normal operation and under accident conditions was evaluated on the basis of a series of experiments that were performed in a scaled test facility. The reactor vessel of the test facility was a 1/10 linear scaled model of a 265-MW pebble bed modular reactor (PBMR), and the RCCS of the test facility was designed to limit the volumetric-averaged reactor vessel wall temperature below the maximum permissible wall temperature of the prototype reactor. The experiments were conducted by simulating the heat released from the reactor vessel wall to the RCCS. The power was reduced by 1/100 to preserve the heat flux, and the timescale was reduced by 1/10 to preserve the stored energy per volume. In the normal operation tests, detailed information on the temperature distribution and heat removal fraction of the upper pool and side pool was obtained. In the loss of all forced convection accident test, the passive afterheat removal capability of the RCCS was evaluated. These experimental results will be used to validate the reactor safety analysis codes and to evaluate the feasibility of the water pool-type RCCS.
