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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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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.
Rahim Nabbi, Wilfried Jahn, Gerhard Meister, Werner Rehm
Nuclear Technology | Volume 62 | Number 2 | August 1983 | Pages 172-189
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT83-A33216
Articles are hosted by Taylor and Francis Online.
Analysis of extreme water ingress accidents in the pebble bed high-temperature reactor of 500-MW(thermal) power during the first few minutes shows that the temperature coefficients of reactivity limit the power increase, presupposing no action of the shutdown system and other safety devices. The rupture of all steam generator tubes with the highest ingress rate of 55 kg/s results in a power maximum of 1.8 times the initial value after ∼1 min. The system pressure increases from the operating value of 40 bar up to the design value of 50 bar. Fuel temperatures do not reach values that cause fuel particle damage and fission product release. Hence, special requirements on the promptness of shutdown rod actions are not needed to limit accident consequences in the core. Overpressurization of the reactor vessel will arise, however, if water ingress with the highest rate continues. Water ingress at a small rate (7 kg/s), corresponding to the rupture of a few tubes, results in a rather slow power increase up to 1.3 times the initial value and to a primary system pressure of 43 bar after 5 min.