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Coiled Tube Gas Heater Effectiveness Modeling, Simulation, and Experiments for Nuclear Power Conversion Cycles

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개인저자Greenop, Andrew.
단체저자명University of California, Berkeley. Nuclear Engineering.
서명/저자사항Coiled Tube Gas Heater Effectiveness Modeling, Simulation, and Experiments for Nuclear Power Conversion Cycles.
발행사항[S.l.] : University of California, Berkeley., 2018
발행사항Ann Arbor : ProQuest Dissertations & Theses, 2018
형태사항117 p.
소장본 주기School code: 0028.
ISBN9780438324985
일반주기 Source: Dissertation Abstracts International, Volume: 80-01(E), Section: B.
Advisers: Per F. Peterson
요약With the growing demand for clean, carbon free electricity around the globe due to industrialization and increasing populations, nuclear reactors will become a necessity to supplement power from intermittent renewable sources. Advanced reactor d
요약In order to design the CTGH specifically for the FHR, it was necessary to simulate the conditions in the FHR. Conventional modeling codes would take too long to model the complex geometry of the CTGH to be an effective design tool, so this disse
요약In order to use THEEM as a design tool, it was necessary to validate the code experimentally. Two different experiments that both used water and air as heat transfer fluids were performed for this purpose. The first experiment primarily served a
요약Once THEEM had gone through initial experimental validation, it could be expanded as a design tool for other applications besides the FHR. First, a parametric study was performed to measure the effect of changing each aspect of the CTGH geometry
일반주제명Nuclear engineering.
언어영어
기본자료 저록Dissertation Abstracts International80-01B(E).
Dissertation Abstract International
대출바로가기http://www.riss.kr/pdu/ddodLink.do?id=T14998344

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