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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.
Mingjun Wang, Annalisa Manera, Victor Petrov, Suizheng Qiu, Wenxi Tian, G. H. Su
Nuclear Technology | Volume 203 | Number 2 | August 2018 | Pages 194-204
Technical Paper | doi.org/10.1080/00295450.2018.1446656
Articles are hosted by Taylor and Francis Online.
In detailed previous work by the authors, an innovative decay heat removal (DHR) system has been proposed and designed for the Integral Inherently Safe Light Water Reactor (I2S-LWR). The current paper studies the inadvertent actuation of one DHR system train during I2S-LWR normal operation due to a false signal or operator action. The RELAP5 code is used to perform a one-dimensional study, and important thermal-hydraulic characteristics, including primary loop coolant flow rate, pressure, temperature, DHR primary-side flow rate, and coolant temperature, are achieved during this transient. Then, a detailed computational fluid dynamics simulation utilizing STARCCM+ is carried out to investigate the coolant mixing characteristics in the downcomer and lower plenum and obtain the local thermal-hydraulic conditions at the reactor core inlet. It is found that as a consequence of inadvertent DHR actuation, the maximum overcooling at the reactor core inlet is about 3 K, which would not result in significant reactivity insertion. Furthermore, a more severe transient of inadvertent DHR operation with intermediate loop break is studied, and the results show that this would not lead to more significant overcooling to the I2S-LWR core compared with inadvertent DHR operation without intermediate loop break. This work is an indispensable supplement for DHR system comprehensive assessment in the I2S-LWR project.