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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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OECD NEA meeting focuses on irradiation experiments
Members of the OECD Nuclear Energy Agency’s Second Framework for Irradiation Experiments (FIDES-II) joint undertaking gathered from September 29 to October 3 in Ketchum, Idaho, for the technical advisory group and governing board meetings hosted by Idaho National Laboratory. The FIDES-II Framework aims to ensure and foster competences in experimental nuclear fuel and structural materials in-reactor experiments through a diverse set of Joint Experimental Programs (JEEPs).
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.
