This paper summarizes the results of a conceptual design study addressing the design and technology development requirements for a high-temperature intermediate heat exchanger (IHX) for the Next Generation Nuclear Plant (NGNP). Results of the study confirmed the incentives for compact heat exchangers and suggested new IHX configurations that provide for maintainability at the heat transfer module level. Scoping analyses provided encouragement that IHX life would not be limited by creep or fatigue effects, given the PBMR NGNP Heat Transport System architecture and operating conditions. However, corrosion rates implied by existing data are troubling for thin sections, and improved characterization of environmental effects was identified as a high priority for technology development.
IHX Design and Development for the Next Generation Nuclear Plant
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Penfield, SR, Jr., Greyvenstein, R, Rittenhouse, PL, & Nash, J. "IHX Design and Development for the Next Generation Nuclear Plant." Proceedings of the Fourth International Topical Meeting on High Temperature Reactor Technology. Fourth International Topical Meeting on High Temperature Reactor Technology, Volume 2. Washington, DC, USA. September 28–October 1, 2008. pp. 29-34. ASME. https://doi.org/10.1115/HTR2008-58130
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