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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.
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.
C. D. Fletcher, L. S. Ghan
Nuclear Technology | Volume 95 | Number 2 | August 1991 | Pages 228-246
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34559
Articles are hosted by Taylor and Francis Online.
Large thermal-hydraulic systems computer codes are most often applied to investigate safety issues in existing nuclear facilities. One such code is applied to aid the design process for a proposed state-of-the-art research reactor. The RELAP5 computer code is used to simulate system response to hypothetical loss-of coolant accidents (LOCAs) in an early design of the Advanced Neutron Source (ANS). Among accident scenarios, a LOCA event is expected to be one of the most challenging to the ANS reactor core; similar analyses for other accident types are in progress. This is the first detailed study of ANS transient system response during accidents, and the outcome of the analysis is used to benefit the design process. The ANS model used is based on an early (preconceptual) cool ing system design layout. This early design has since been superseded by an improved design that is partly based on the results of these studies. The calculated responses of the early design to representative LOCA events are described; the simulations indicate that fuel melting and damage would be experienced for medium and large breaks. The effectiveness of employing a gascharged accumulator on the primary coolant system for preventing fuel damage following medium- and large-break LOCAs is evaluated. As a result of this evaluation, the new ANS design incorporates such accumulators. Analysis uncertainties are addressed, and the findings from this study that were used for the next phase of ANS design are highlighted.