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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.
Jun Feng, Frank A. McClintock, Rui Vieira, Regis M. Pelloux, Richard J. Thome
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1177-1182
Ignition Device | doi.org/10.13182/FST91-A29502
Articles are hosted by Taylor and Francis Online.
The conductor for the central solenoid of the Compact Ignition Tokamak (CIT) operates with a multiaxial stress condition in which the ratios of the principal stresses are not proportional during the operating cycle. The stresses arise from both the self-electromagnetic loads and interactions with the toroidal field coils. The latter primarily provide a radial compressive load which varies during a pulse. This paper presents the status of conductor evaluation and design criteria development. Analysis of the stress conditions during a pulse indicates that the bulk of the fatigue life damage is done during one portion of the total current scenario. This is based on the postulate that the multiaxial stress and lifetime condition can be characterized approximately by examining the worst combination of shear stress range with tensile stress normal to the shear plane at reversal. The latter is found by tracing the history of the principal shear stresses and their associated normal stresses for all three principal shear planes at the worst point in the coil. The analysis thus provides the operating conditions to be simulated in uniaxial and multiaxial tests from which lifetime correlations can be found for the conductor. Evaluation of existing multiaxial fatigue life data on Alloy 718 has led to a postulate for a criterion to be applied to the conductor. Uniaxial and biaxial data are being taken on candidate conductors to verify the postulated lifetime correlations. The primary candidates for the conductor are C15715 (an alumina-dispersion-strengthened copper) and a CuCrZr alloy. The conductor will be required in plate form, nominally 1-inch thick and 70-inches square. Tests have thus far only been conducted on specimens from subscale plates. The status of the test program and of the full-scale plate development program are given.