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Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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Education and training to support Canadian nuclear workforce development
Along with several other nations, Canada has committed to net-zero emissions by 2050. Part of this plan is tripling nuclear generating capacity. As of 2025, the country has four operating nuclear generating stations with a total of 17 reactors, 16 of which are in the province of Ontario. The Independent Electricity System Operator has recommended that an additional 17,800 MWe of nuclear power be added to Ontario’s grid.
Maman Kartaman Ajiriyanto, Aslina Br. Ginting, Sungkono, Supardjo, Juan Carlos Sihotang
Nuclear Technology | Volume 211 | Number 5 | May 2025 | Pages 953-962
Research Article | doi.org/10.1080/00295450.2024.2365485
Articles are hosted by Taylor and Francis Online.
Post-irradiation examination (PIE) of a low-enriched-uranium silicide fuel plate, irradiated in the Indonesian Reaktor Serba Guna–Gerrit Augustinus Siwabessy (RSG-GAS) multipurpose reactor, was successfully conducted. The objective of the PIE project was to evaluate the performance and integrity of the fuel under radiation exposure and, furthermore, to explore the potential for increasing the burnup level, enhancing its efficiency and effectiveness. The targeted fuel plate, identified as IDA0045, was extracted from the experimental silicide fuel element RI-SIE2, which had a burnup level of approximately 56% loss of 235U. A scanning electron microscope combined with energy dispersive X-ray spectroscopy microstructural examination and a Vickers microhardness test were conducted for the top, middle, and bottom sections of the fuel. The PIE results indicated minimal occurrence of fuel swelling and good fuel integrity under irradiation, suggesting the possibility of increasing the burnup level.