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Division Spotlight
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
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.
Yassin A. Hassan
Nuclear Technology | Volume 69 | Number 3 | June 1985 | Pages 257-267
Technical Paper | Fission Reactor | doi.org/10.13182/NT85-A33609
Articles are hosted by Taylor and Francis Online.
Three-dimensional fluid and thermal mixing analysis of a full-scale cold leg and downcomer of a Babcock & Wilcox-designed pressurized water reactor is performed. The impetus of the present study is to provide an accurate estimation of the local fluid temperatures in the cold leg and downcomer when the cold high-pressure safety fluid is injected into the cold leg carrying a hot fluid. Such temperature predictions are needed in resolving the so-called pressurized thermal shock issue in the nuclear industry. The unique feature of this study is the use of the accurate mass-flow-weighted skew-upwind scheme to approximate the convective transport terms in the COMMIX-1A code approximation of the fluid energy equation. This new scheme is shown to considerably reduce the false diffusion that plagued multidimensional thermal-hydraulic applications. The computed fluid velocity patterns and temperature predictions have shown similar behavior to the flow visualization and temperature field measurements in scaled experiments.