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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
Taisuke Yonomoto, Yutaka Kukita, Yoshinari Anoda, Hideaki Asaka
Nuclear Technology | Volume 109 | Number 3 | March 1995 | Pages 338-345
Technical Paper | Nuclear Reactor Safety | doi.org/10.13182/NT95-A35082
Articles are hosted by Taylor and Francis Online.
Two experiments were conducted at the ROSA-V/Large-Scale-Test-Facility to investigate thermal-hydraulic behavior of a gravity-driven passive injection system for a pressurized water reactor under cold-leg small break loss-of-coolant accident conditions. The injection system, used in the tests, consisted of a tank located above the reactor vessel, an injection line, and pressure balance lines. The two tests were conducted using the same break area, corresponding to 2.5% of the scaled cold-leg cross-sectional area, and different actuation logic for the automatic depressurization system (ADS). Both experimental results showed an accumulation of hot water in the upper part of the tank due to the natural circulation, followed by a continuous water level drop, and the existence of a slightly superheated liquid layer near the water surface. Because of the differences in the ADS actuation logic, the system depressurization behavior was different between the two tests. Much larger injection rates from the tank were obtained for the test that experienced the larger depressurization rate. The liquid temperature distributions obtained from these tests were predicted well by an analytical model proposed in a previous paper.