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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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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
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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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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.
A. J. Buslik, R. E. Hall
Nuclear Technology | Volume 46 | Number 3 | December 1979 | Pages 566-570
Technical Paper | Nuclear Power Reactor Safety / Reactor | doi.org/10.13182/NT79-A32367
Articles are hosted by Taylor and Francis Online.
A calculation of the probability distributions for the radioactive releases of 131I and 133Xe in a steam generator tube rupture accident is given; the effects of iodine spiking are included. The accident sequence considered involves loss of off-site power after the steam generator tube rupture. Two models are considered for iodine release, one of which yields upper bound releases, and the other of which is our best-estimate model. With the best-estimate model, the probability of a 131I release >2 Ci is 1 × 10−6 per reactor-year. With the upper bound model, the probability of a 131I release >66 Ci is 1 × 10−6 per reactor-year. The probability of a release exceeding 600 Ci of 133Xe is 2 × 10−6 per reactor-year.
