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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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
Yongwei Chen, Zeyong Zhang, Dong Li
Nuclear Technology | Volume 204 | Number 3 | December 2018 | Pages 378-385
Technical Paper | doi.org/10.1080/00295450.2018.1477394
Articles are hosted by Taylor and Francis Online.
To effectively reduce the probability of instrumentation and control (I&C) equipment aging failures in nuclear power plants, a preventive replacement aging treatment strategy should be adopted. A single failure–oriented and component aging sensitivity classification model is put forward to classify I&C equipment aging in nuclear power plants, and three methods for assessing I&C equipment life cycles (i.e., aging tests, standards and specifications, and failure data) are provided. Meanwhile, provided with the characteristic curves of I&C equipment aging failures in nuclear power plants, specific aging treatment steps are put forward, including (1) defining the scope of aging treatment in horizontal and longitudinal dimensions of signal flow direction and equipment composition; (2) determining the aging treatment implementation cycle by a life cycle margin setting method; (3) refining the aging treatment implementation process by division of four stages, namely, aged equipment classification, aging data management, aging treatment implementation, and aging testing feedback, to ensure reliable and safe operation of I&C equipment in nuclear power plants.
