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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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Fusion Science and Technology
February 2024
Latest News
Lightbridge announces first U-Zr fuel rod samples extruded at INL
Lightbridge Corporation announced today that it has reached “a critical milestone” in the development of its extruded solid fuel technology. Coupon samples using an alloy of zirconium and depleted uranium—not the high-assay low-enriched uranium (HALEU) that Lightbridge plans to use to manufacture its fuel for the commercial market—were extruded at Idaho National Laboratory’s Materials and Fuels Complex.
C. Poletiko, P. Trabuc, J. Durand, B. Tormos, L. Pignoly
Fusion Science and Technology | Volume 48 | Number 1 | July-August 2005 | Pages 194-199
Technical Paper | Tritium Science and Technology - Decontamination and Waste | doi.org/10.13182/FST05-A910
Articles are hosted by Taylor and Francis Online.
Due to its high diffusivity and different trapping phenomena, tritium is present in materials, such as steels which are in use in different parts of a nuclear power reactor or even in graphite which is present in fusion reactor.From waste management point of view, it is necessary to know as accurately as possible the tritium inventory in such materials before disposal. Moreover the knowledge of tritium species (HTO or HT. . .) is also a significant information in case of detritiation prior to storage, since countries regulation already limit tritium contents and releases. There are three different strategies for tritiated waste management. The first one consists in a storage with confinement packages the second one is waiting for radioactive decay. The third one consists in the application of detritiation processes.Studies have been performed to determine different processes that could be used for tritium removal. The aim of this paper was, to study, at laboratory scale, different procedures which may be used for stainless steels and carbon materials detritiation.Thermal detritiation kinetics till 1300 K has been studied under various atmospheres; full chemical dissolution of samples has also been performed both for steel and graphite, this to perfectly know the tritium content in such matrices. Finally a study of tritium content in steel layers has also been made, to learn about the tritium behaviour. All results are given, allowing the possibility to take a decision either for detritiation procedure or storage conditions.The main result is that thermal out-gassing enables higher than 95 % tritium extraction from the bulk at temperature in the range of 600K, without any material destruction under Hytec gas (Ar + 5% volume H2).