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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
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
From South Korea to Belgium: Testing a high-density research reactor fuel
The Korea Atomic Energy Research Institute has developed a high-density uranium silicide fuel designed to replace high-enriched uranium in research reactors. Recent irradiation tests appear to be successful, KAERI reports, which means the fuel could be commercialized to continue a key global nuclear nonproliferation effort—converting research reactors to run on low-enriched uranium fuel.
P. Agg, J.P. Krasznai, A.B. Antoniazzi, R.E. Massey, B. Fishbein, R. Mowat
Fusion Science and Technology | Volume 28 | Number 3 | October 1995 | Pages 1097-1103
Tritium Properties and Interaction with Material | Proceedings of the Fifth Topical Meeting on Tritium Technology In Fission, Fusion, and Isotopic Applications Belgirate, Italy May 28-June 3, 1995 | doi.org/10.13182/FST95-A30553
Articles are hosted by Taylor and Francis Online.
The behaviour of tritium in the body, as a result of intakes from contact with tritium contaminated surfaces and the subsequent radiation dose impact, is dependent on the nature of the tritium species. Research over the past few years has yielded important insight into the nature of tritiated species on surfaces exposed to elemental tritium. A significant drawback to understanding the relationship between tritium exposure and dose however is that most surface characterization data, reported in the literature, was generated at high temperature, whereas, exposure to tritiated surfaces occurs mostly at ambient temperature. In this paper we describe the results of characterization studies carried out at both ambient and high temperature. The well characterized stainless steel specimens were subsequently used in animal exposures.