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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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Fusion Science and Technology
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.
Yuzhong Jin, Wei Zhao, Christopher Watts, James P. Gunn, Guangwu Zhong, Xiang Liu
Fusion Science and Technology | Volume 75 | Number 2 | February 2019 | Pages 120-126
Technical Paper | doi.org/10.1080/15361055.2018.1520577
Articles are hosted by Taylor and Francis Online.
An all-welded ITER divertor Langmuir probe (DLP) model was analyzed by ANSYS 17.0. Temperature field and surface convective heat transfer were obtained by fluid analysis using ANSYS/CFX under both steady-state (10 MW/m2) and slow transient-state (20 MW/m2 for 10 s) working conditions. Mechanical analysis was performed with the temperature field as the preloading condition. The equivalent von-Mises stress and plastic strain distribution have been obtained. The analyzed results show that the DLPs would withstand very high temperature, which can reach 1852°C mainly owing to the extremely high heat flux as well as photon irradiation. The maximum temperature of the copper connection between the DLP and the monoblock would be 792°C, demonstrating that the bonding structure would not be destroyed. All the materials except the alumina pipe have undergone plastic yield analysis, implying that a low cycle strain-fatigue analysis needs to be done in the near future.