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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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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.
Karl Verfondern, Werner Schenk, Heinz Nabielek
Nuclear Technology | Volume 91 | Number 2 | August 1990 | Pages 235-246
Technical Paper | Safety of Next Generation Power Reactor / Fuel Cycle | doi.org/10.13182/NT90-A34431
Articles are hosted by Taylor and Francis Online.
The high fission product retention potential of coated particle fuel combined with inherently passive temperature controls guarantee almost complete fission product retention during an accident in a small modular high-temperature reactor. Extensive experimental results provide the basis for this claim to inherent safety. Models and codes have been developed to (a) predict realistic, or at least conservative, overall release rates from the primary circuit, (b) reduce the large number of experimental results to a small set of characteristic coefficients, and (c) predict release beyond experimental conditions. Conservative predictions of release from the core have been done using a traditional pressure vessel model for release from fuel particles and simplified diffusion models for fission product transport. This approach is based on experimental work that has been done on nearly all possible accident conditions and is limited by the finite number of experiments. Data reduction has been achieved with two different modeling approaches combined into a new model that is equally relevant to all volatile fission products. The safety design of the 200-MW(thermal) HTR-Modul is based on Kernforschungsanlage Jülich experimental results from fuel accident condition performance testing and the modeling effort has been applied to a safety review.