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Materials in Nuclear Energy Systems (MiNES 2023)
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From the pages of Nuclear News: Industry update November 2023
Here is a recap of industry happenings from the recent past:
Centrus-Oklo partnership expands
Oklo, a California-based developer of next-generation fission reactors, has expanded its partnership with Centrus Energy, a Maryland-based supplier of nuclear fuel and services. The two companies have been cooperating since 2021 on the development of Centrus’s American Centrifuge Plant in Piketon, Ohio, to produce high-assay low-enriched uranium (HALEU) fuel. According to the companies’ new memorandum of understanding, Centrus will manufacture certain components for Oklo’s Aurora “powerhouse” reactor, a fast neutron reactor designed to generate up to 15 MW of power and operate for at least 10 years without refueling. The Aurora is also designed to produce usable heat. Centrus also has agreed to purchase electricity generated by the Aurora reactors, while Oklo has agreed to purchase HALEU fuel from the Piketon facility. The facility is expected to begin fuel production before the end of the year.
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.