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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.
T.Tanifuji, S. Jitsukawa, S.Nasu, A.Moon, K.Mori, S.Nishikawa, M.Yamanaka, Y.Izawa
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 954-957
Material Interaction and Permeation | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22726
Articles are hosted by Taylor and Francis Online.
We investigated tritium (T) release behavior from silica glass. The specimens were 8 kinds of commercially available silica glass. T was injected by the 6Li (n,α)T reaction of sintered pellets of lithium oxide (Li2O) into the silica glass with thermal neutrons in JRR-2 (VT-8) up to 5 × 1018 neutrons/cm2 at ambient temperature (about 350 K). After irradiation, the Li2O pellets were removed from the silica glass, and T release from the silica glass was measured in a flow of hydrogen (H2) or ammonia (NH3) sweep gas at atmospheric pressure at a constant heating rate of 2 K/min between 675 K and 1375 K with a proportional counter. In the case of H2 sweep gas, a maximum tritium release rate was observed around 1023 K, while in the case of NH3 sweep gas, two peaks around 1023 K and around 1123 K or a peak around 1123 K with a shoulder were obserbed. After the experiments of T release, FT-IR spectra showed a decrease of SiOH bands at 3650 cm−1. On the other hand, no changes in intensities at 2250 cm−1 due to SiH were observed for both samples before and after T release.
