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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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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.
Wei Xu, Jianhua Xia, Xiaojing Liu, Xu Cheng, Wei Zeng
Nuclear Technology | Volume 205 | Number 1 | January-February 2019 | Pages 281-296
Technical Paper | doi.org/10.1080/00295450.2018.1457887
Articles are hosted by Taylor and Francis Online.
Bottom reflooding is the third phase when a large-break loss-of-coolant accident occurs. Due to the complexity and importance, especially in a distinct narrow rectangular channel, various research methods can be utilized to understand the whole process. Test facility is established to figure out the thermal-hydraulic behaviors during bottom reflooding, and the acquisition of accurate solid temperature is essential. The inverse heat transfer problem method is applied to take full advantage of experimental data. In addition, a bottom reflooding transient (BRT) code is utilized to calculate various parameters conveniently. A three-dimensional heat conduction equation for a transient state is solved implicitly to obtain solid temperature distribution, surface heat flux, and heat transfer coefficient at the cooling surface. The simulation results of the BRT code are compared with that of RELAP5, an available system code, and the experimental results. A conclusion that can be derived is that the BRT code shows good applicability of simulating bottom reflooding in a narrow rectangular channel.