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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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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. Tobin, V. Karpenko, A. Burnham, R. Peterson
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 457-463
National Ignition Facility | doi.org/10.13182/FST96-A11962983
Articles are hosted by Taylor and Francis Online.
The National Ignition Facility (NIF) will be configured in its baseline design to achieve ignition and gain using the indirect drive approach. However, the NIF primary criteria and functional requirements require the NIF design “to not preclude” the ability to conduct inertial confinement fusion experiments using the direct drive approach.
The direct drive approach requires symmetrical illumination of an inertial confinement fusion (ICF) capsule where each beam fully subtends the capsule. Therefore, the re-directing of 24 of the 48 NIF beamlines (each consisting of a 2 × 2 beamlet group) from ~30° and ~50° cone angles to ~75° cone angles located near the chamber ‘equator’ is required. This would be accomplished by adjusting intermediate transport mirrors such that the beams would intercept different final mirrors in the Target Bay and be directed into final optics assemblies attached to the chamber at the new port locations. Allowing space to be able to convert from one irradiation scheme to another while fully meeting the mechanical stability requirements for each approach is a significant challenge. Additionally, NIF user needs (features supporting weapons physics, weapons effects, inertial fusion energy, or Basic Energy Sciences) cannot be compromised by direct drive needs.
The target for direct drive, absent a hohlraum, emits much fewer cold x rays than in the indirect drive case. Further, the irradiation scheme, by its nature, may not result in the absorption of all of the 3ω light and therefore could create a unique hazard to the NIF chamber first wall of significant fluences of scattered UV laser light. This paper describes possible design features of the NIF Target Area to allow conversion to a direct drive capability, and discusses some of the differences in post-shot conditions created compared to indirect drive.