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2025 ANS Annual Conference
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Chicago, IL|Chicago Marriott Downtown
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High-temperature plumbing and advanced reactors
The use of nuclear fission power and its role in impacting climate change is hotly debated. Fission advocates argue that short-term solutions would involve the rapid deployment of Gen III+ nuclear reactors, like Vogtle-3 and -4, while long-term climate change impact would rely on the creation and implementation of Gen IV reactors, “inherently safe” reactors that use passive laws of physics and chemistry rather than active controls such as valves and pumps to operate safely. While Gen IV reactors vary in many ways, one thing unites nearly all of them: the use of exotic, high-temperature coolants. These fluids, like molten salts and liquid metals, can enable reactor engineers to design much safer nuclear reactors—ultimately because the boiling point of each fluid is extremely high. Fluids that remain liquid over large temperature ranges can provide good heat transfer through many demanding conditions, all with minimal pressurization. Although the most apparent use for these fluids is advanced fission power, they have the potential to be applied to other power generation sources such as fusion, thermal storage, solar, or high-temperature process heat.1–3
Manorma Kumar, Guillem Cortes Rossell
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 661-673
Review Article | doi.org/10.1080/00295450.2024.2356328
Articles are hosted by Taylor and Francis Online.
The paper is focused on how to apply the probabilistic safety assessment (PSA) methodology to assess the nuclear safety risks associated with the transportation of radioactive material. The methodology is comprehensive and covers the different modes of transport (for example, by road, by train, by ship, and by air) used for the transportation of radioactive material. The proposed methodology can be applied to any specific mode of transportation of radioactive material as well as to any specific country. This paper focuses on application of this methodology for transportation of radioactive material by train.
The systematic assessment starts with the identification of the risk associated with the transportation mode and its initiating events to analyze what can go wrong in the transportation of radioactive material and how likely it can be. An accident involving radioactive material has sensitive information, and such information is not publicly available. Therefore, generic accident data can be utilized to develop probabilistic models and quantify the risk associated with radioactive material transportation. Another fact is that radioactive material transportation accidents are extremely rare; hence, associated statistics are insufficient for the development of PSA models, so generic accident data can be used to predict accident frequency.
The paper explores the feasibility of using probabilistic methods to assess the safety risks associated with radioactive material transport. The paper describes how to perform a comprehensive probabilistic assessment and create a generic accident event tree that is based on train accident data. The focus of the event tree is to outline a range of different train accident scenarios and their respective probabilities of occurrence and their consequences.
