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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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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.
M. B. Kowalsky, J. Birkholzer, J. Peterson, S. Finsterle, S. Mukhopadhyay, Y. Tsang
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 169-179
Technical Paper | Tough206 | doi.org/10.13182/NT08-A4017
Articles are hosted by Taylor and Francis Online.
We describe a joint inversion approach that combines geophysical and thermal-hydrological data for the estimation of (a) thermal-hydrological parameters (such as permeability, porosity, thermal conductivity, and parameters of the capillary pressure and relative permeability functions) that are necessary for predicting the flow of fluids and heat in fractured porous media and (b) parameters of the petrophysical function that relates water saturation, porosity, and temperature to the dielectric constant. The approach incorporates the coupled simulation of nonisothermal multiphase fluid flow and ground-penetrating radar (GPR) travel times within an optimization framework. We discuss application of the approach to a large-scale in situ heater test that was conducted at Yucca Mountain, Nevada, to better understand the coupled thermal, hydrological, mechanical, and chemical processes that may occur in the fractured rock mass around a geologic repository for high-level radioactive waste. We provide a description of the time-lapse geophysical data (i.e., cross-borehole GPR) and thermal-hydrological data (i.e., temperature and water content data) collected before and during the 4-yr heating phase of the test and analyze the sensitivity of the most relevant thermal-hydrological and petrophysical parameters to the available data. To demonstrate feasibility of the approach, and as a first step toward comprehensive inversion of the heater test data, we apply the approach to estimate a single parameter: the permeability of the rock matrix.