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Division Spotlight
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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Nuclear News 40 Under 40 discuss the future of nuclear
Seven members of the inaugural Nuclear News 40 Under 40 came together on March 4 to discuss the current state of nuclear energy and what the future might hold for science, industry, and the public in terms of nuclear development.
To hear more insights from this talented group of young professionals, watch the “40 Under 40 Roundtable: Perspectives from Nuclear’s Rising Stars” on the ANS website.
D. L. Hillis, J. T. Hogan, P. Andrew, J. Ehrenberg, M. Groth, M. von Hellermann, L.D. Horton, R. Monk, P. Morgan, M. Stamp
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 941-945
Plasma Facing Components Technology (Poster Session) | doi.org/10.13182/FST98-A11963734
Articles are hosted by Taylor and Francis Online.
Future fusion reactors, like ITER, will rely on an active exhaust system to pump tritium (T) in the divertor and then recirculate it to the fuel stream. Estimation of the T inventory requires a detailed T balance, which determines if T is preferentially enriched relative to D in its pathway from the main plasma to the divertor and pump. On the Joint European Torus (JET), the neutral T concentration in the sub-divertor (pumping plenum and region below the divertor strike point plate) is measured with a modified Penning gauge coupled to a high-resolution spectrometer. In addition, T concentration measurements are made in the plasma edge and strike point region with a spectrometer viewing these regions. The sub-divertor and divertor (region above the strike point plate) T concentration measurements show differences during initial T uptake and retention which are characteristic of wall deposition properties. Since wall retention is one of the factors in calculating the eventual T inventory in a reactor, a detailed study of this process has been undertaken.