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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.
Kazys K. Almenas, Joseph M. Marchello
Nuclear Technology | Volume 41 | Number 3 | December 1978 | Pages 263-275
Technical Paper | Reactor | doi.org/10.13182/NT78-A32112
Articles are hosted by Taylor and Francis Online.
The effect of a mechanistic drop evaporation model on the pressure-temperature transient of a containment under loss-of-coolant accident (LOCA) conditions has been investigated. To implement the model, the traditional two-node lumped parameter (atmosphere and sump) had to be expanded to encompass additional open thermodynamic systems. The calculations were compared against results obtained by a widely employed containment analysis code using the instantaneous evaporation model. The mechanistic drop evaporation model was found to produce higher peak pressures and substantially higher degrees of superheat for a steam line break LOCA. The dependence of pressure in both saturated and superheated air-steam atmospheres was generalized in terms of normalized pressure-energy derivatives. For superheated atmospheres, these derivatives were found to depend on the mode of energy removal. Two idealized energy removal modes were defined (purely condensing and purely noncondensing). The normalized pressure-energy derivatives for these mechanisms were found to differ by a factor of 2 to 3 for the parameter range of interest to containment analysis.