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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
2027 ANS Winter Conference and Expo
October 31–November 4, 2027
Washington, DC|The Westin Washington, DC Downtown
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
Supreme Court rules against Texas in interim storage case
The Supreme Court voted 6–3 against Texas and a group of landowners today in a case involving the Nuclear Regulatory Commission’s licensing of a consolidated interim storage facility for spent nuclear fuel, reversing a decision by the 5th Circuit Court of Appeals to grant the state and landowners Fasken Land and Minerals (Fasken) standing to challenge the license.
D. N. Sah, C. S. Viswanadham, Sunil Kumar, P. R. Roy
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 136-146
Technical Paper | Fission Reactor | doi.org/10.13182/NT89-A34236
Articles are hosted by Taylor and Francis Online.
Samples of Zircaloy-2 cladding from four UO2 fuel elements irradiated in the Tarapur Atomic Power Station boiling water reactor up to fuel burnup levels of 9599 to 12 627 MWd/tonne U are examined using scanning electron microscopy and electron probe microanalysis to study the nature of deposits formed on the inner surface of the cladding. The clad samples from one fuel element that was located nearest to the control blade and had a fission gas release of 3.7% have deposits on the surface. Uranium, zirconium, cesium, oxygen, tellurium, barium, tin, and rubidium are present in the deposit. The deposit is composed of two layers: a layer toward the fuel, containing mainly uranium, cesium, and oxygen, and another toward the cladding, containing uranium, zirconium, cesium, and oxygen. The formation of the deposits is explained by a localized high release of volatile fission products from the fuel and their migration to the clad surface.
