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2025 ANS Annual Conference
June 15–18, 2025
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
D. B. MacMillan
Nuclear Science and Engineering | Volume 39 | Number 3 | March 1970 | Pages 329-336
Technical Paper | doi.org/10.13182/NSE70-A19994
Articles are hosted by Taylor and Francis Online.
A mathematical method is described for the computation of the probability distribution of neutron populations in a point reactor with a weak source. The author and his colleagues have previously described a method for doing such computations, and G. I. Bell has described a different method; the present paper uses ideas from both of these older methods plus new formulations for computing the probability distribution from values of the generating function, for evaluating the probability distribution of precursor decay rates instead of that of neutron populations, and for evaluating the effect of short neutron lifetime without using unnecessarily short time steps in numerical integration. As a result, the method presented here is more widely applicable and more accurate than the older methods. The reactor model used here permits taking account of six delayed-neutron precursor groups and of finite neutron lifetime.