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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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
Sellafield awards $3.86B in infrastructure contracts to three companies
Sellafield Ltd., the site license company overseeing the decommissioning of the U.K.’s Sellafield nuclear site in Cumbria, England, announced the award of £2.9 billion (about $3.86 billion) in infrastructure support contracts to the companies of Morgan Sindall Infrastructure, Costain, and HOCHTIEF (UK) Construction.
Jong-Dae Hong, Euijung Kim, Yong-Sik Yang, Dong-Hak Kook
Nuclear Technology | Volume 203 | Number 3 | September 2018 | Pages 282-292
Technical Paper | doi.org/10.1080/00295450.2018.1448203
Articles are hosted by Taylor and Francis Online.
One of the limiting mechanisms of pressurized water reactor spent fuel cladding is creep owing to high temperature and rod internal pressure. Based on extensive studies, many countries have tentatively concluded that creep rupture is hard to occur under dry storage conditions and cannot severely degrade the integrity of the cladding if it meets the 400°C limitation owing to a self-limiting property. However, the changes in mechanical properties after creep deformation are not well understood due to the limited amount of relevant tests and analyses. In this regard, mechanical property degradation of unirradiated Zircaloy-4 cladding by creep deformation was investigated using a ring compression test and microscopic observation. In addition, the implication regarding spent fuel cladding integrity based on the test results is described.