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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
Sri Sudadiyo
Nuclear Technology | Volume 211 | Number 4 | April 2025 | Pages 645-660
Review Article | doi.org/10.1080/00295450.2024.2352663
Articles are hosted by Taylor and Francis Online.
The mean time between failures (MTBF) estimation has been intensively investigated in recent years. MTBF can be used to decide on a maintenance strategy or inspection timeline intervals for the RSG-GAS reactor (or GAS multipurpose reactor). The RSG-GAS reactor is a pool-type reactor where light water is used as a moderator, coolant, and shielding. The purpose of this paper is to propose the nonhomogeneous Poisson process (NHPP) model to obtain the MTBF estimation value. Thus, the RSG-GAS reactor installation would have higher safety, a longer lifetime, and substantial reliability with a minor failure rate, including the subcomponents of the JE01-AP03 primary centrifugal pump.
In this research work, the methodology processes data accumulation and estimates the parameters of the NHPP model to determine the maintenance schedule or inspection timeline intervals based on the MTBF value when the confidence level reaches the targeted percentage. The results indicate that a MTBF estimation has been acquired for the RSG-GAS reactor installation. In the implemented case, an inspection timeline is defined for the JE01-AP03 primary centrifugal pump with a reliability growth value of 0.41 and a MTBF estimation circa 42 days.
