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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Marcel Straetz, Rainer Mertz, Jöerg Starflinger (Univ of Stuttgart)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 815-824
In the frame of the EU-funded sCO2-HeRo (supercritical carbon dioxide heat removal) project a heat removal system, based upon a Brayton cycle using supercritical CO2 as working fluid, is currently under investigation. The system should be able to work as a self-launching, self-propelling and self-sustaining decay heat removal system to be retrofitted to existing light water reactors. In case of an accident in a nuclear power plant with the combined initiating events of a station blackout and the loss of the ultimate heat sink this additional heat removal system will transfer the decay heat from the reactor core to the diverse ultimate heat sink, e.g. the ambient air. The system consists of a turbine, compressor, generator, compact heat exchanger and a gas cooler. Since the turbine of the turbo-compressor-system (TCS) provides more power than it is needed for the compressor, the system is self-sustaining and the excess electricity of the generator can be used for auxiliary devices of the power plant. To demonstrate the feasibility of this system, a small-scale demonstrator unit will be attached to the PWR glass model at Gesellschaft für Simulatorschulung (GfS), Essen, Germany. The components of the system will be designed, manufactured and experimental investigated within the sCO2-HeRo project. To determine the design of the compact heat exchanger for the glass model application, which is the objective of the Institute of Nuclear Technology and Energy Systems (IKE), experimental investigations on heat transfer between condensing steam and sCO? were performed in the SCARLETT laboratory. Based upon these experimental results, the compact heat exchanger was designed, manufactured, tested and delivered to GfS.