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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
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.
J. E. Klein, J. R. Wermer
Fusion Science and Technology | Volume 41 | Number 3 | May 2002 | Pages 776-781
Hydride and Storage | Proceedings of the Sixth International Conference on Tritium Science and Technology Tsukuba, Japan November 12-16, 2001 | doi.org/10.13182/FST02-A22690
Articles are hosted by Taylor and Francis Online.
For metal hydride bed disposal, tritium can be exchanged or replaced with deuterium or protium through successive dilution and removal. Analytical expressions are derived to describe the batch isotopic exchange process for metal hydrides with and without isotopic separation by the hydride. For the case without isotopic separation and the hydride being desorbed to the same gas inventory each exchange cycle, simple mathematical expressions are obtained. These equations can be used to estimate the number of exchange cycles needed to reduce the tritium content of a hydride to the desired inventory. Isotopic exchange predictions agreed with experimental results for La-Ni-Al alloys and titanium hydrides.