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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
Kune Y. Suh
Nuclear Technology | Volume 106 | Number 3 | June 1994 | Pages 274-291
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT94-A34958
Articles are hosted by Taylor and Francis Online.
A fast-running computational model has been developed that deals with the nuclear steam supply system heat sink as a two-dimensional slice of steel with its inner and outer surfaces subjected to different thermal and material boundary conditions imposed by such surrounding media as core material, steel layer, water, and gas. This model is generally applicable to two- or one-dimensional heat sinks in the process of heatup and cooldown including liquefaction and resolidification. The numerical model and its solution technique were validated against a set of well-defined initial and boundary value problems. The computer model was applied to analyzing the temperature response of the lower head in a pressurized water reactor large-break loss of coolant accident (LOCA) with ex-vessel cooling. It was of importance to properly account for radiative heat transfer between the two exposed surfaces of the heat sink and the debris bed in the lower plenum, incorporating the physically based view factors, and to allow the heat sink to melt and relocate to the lower plenum. The model was also applied to analyzing the thermal behavior of the lower head in a boiling water reactor large-break LOCA without ex-vessel cooling. It was indicated that the vessel lower head could undergo a noticeable ablation due to the decay power generated from the debris bed in the absence of external cooling. The computer model was demonstrated to produce consistent results for the applications of practical interest in the severe accident arena.