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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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
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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.
Hirofumi Nakamura, Takumi Hayashi, Yasunori Iwai, Masataka Nishi
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 894-898
Divertor and Plasma-Facing Components | doi.org/10.13182/FST01-A11963353
Articles are hosted by Taylor and Francis Online.
Effect of annealing on the transient permeation behavior of deuterium implanted into pure tungsten was investigated. Permeation experiment was carried out with pure tungsten foils (34 mm in diameter, 25 micro-m in thickness, and 99.5% purity) annealed at 1273 K for 3 hours in vacuum and unannealed one. Those permeation characteristics at transient state were analyzed by TMAP4 code. As a result, the feature of the trap site in the unannealed tungsten specimen was revealed that which has about 0.9 eV trap energy and 40ppm-trap density. By the analysis of the permeation behavior through the annealed tungsten, above trap sites disappeared by specimen annealing, and the permeation through annealed tungsten was found to be expressed by simple diffusion equation with the effective diffusion coefficient. However, it may involve the trapping parameter, which is virtually indistinguishable from reduction of diffusion coefficient, in itself.