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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
El Salvador: Looking to nuclear
In 2022, El Salvador’s leadership decided to expand its modest, mostly hydro- and geothermal-based electricity system, which is supported by expensive imported natural gas and diesel generation. They chose to use advanced nuclear reactors, preferably fueled by thorium-based fuels, to power their civilian efforts. The choice of thorium was made to inform the world that the reactor program was for civilian purposes only, and so they chose a fuel that was plentiful, easy to source and work with, and not a proliferation risk.
N. Chikhi, P. Fouquart, J. Delacroix, P. Piluso
Nuclear Technology | Volume 205 | Number 1 | January-February 2019 | Pages 200-212
Technical Paper | doi.org/10.1080/00295450.2018.1486160
Articles are hosted by Taylor and Francis Online.
In-vessel retention (IVR) is an attractive strategy to mitigate a severe accident. However, because of low margins, it remains questionable for reactors of power of 1000 MW(electric) and higher. The success of the IVR strategy mainly depends on the mechanical behavior of the vessel after being ablated and on the inner thermal load, i.e., the heat flux transferred by the molten pool to the vessel, which has to remain lower than the critical heat flux. In some configurations, the stratification of the molten pool may lead to heat flux concentration in the thermal conductive metallic layer. An understanding of the metal layer behavior is fundamental in order to estimate the inner thermal load and requires knowing the liquid-metal physical properties, such as density and surface tension. In the present paper, original data of vessel thermophysical properties are proposed for the first time. Measurements of Type 304L stainless steel and 16MND5 ferritic steel density and surface tension have been made using the sessile drop method. Samples have been melted to form a drop on a yttria-stabilized zirconia substrate and heated up to 200°C above the melting point. Low Bond Axisymmetric Drop Shape Analysis has been used to estimate the sample density and surface tension and to propose correlations for the density and surface tension as a function of temperature. The influence of steel properties on metal layer cooling has been discussed. Especially, the sign of the metal temperature surface tension coefficient was found to be most likely positive. In this case, the Bénard-Marangoni flow is opposite to the Rayleigh-Bénard convection flow.