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020 ▼a 9780438324985
035 ▼a (MiAaPQ)AAI10817269
035 ▼a (MiAaPQ)berkeley:17905
040 ▼a MiAaPQ ▼c MiAaPQ ▼d 248032
0820 ▼a 539.76
1001 ▼a Greenop, Andrew.
24510 ▼a Coiled Tube Gas Heater Effectiveness Modeling, Simulation, and Experiments for Nuclear Power Conversion Cycles.
260 ▼a [S.l.] : ▼b University of California, Berkeley., ▼c 2018
260 1 ▼a Ann Arbor : ▼b ProQuest Dissertations & Theses, ▼c 2018
300 ▼a 117 p.
500 ▼a Source: Dissertation Abstracts International, Volume: 80-01(E), Section: B.
500 ▼a Advisers: Per F. Peterson
5021 ▼a Thesis (Ph.D.)--University of California, Berkeley, 2018.
520 ▼a With 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
520 ▼a In 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
520 ▼a In 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
520 ▼a Once 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
590 ▼a School code: 0028.
650 4 ▼a Nuclear engineering.
690 ▼a 0552
71020 ▼a University of California, Berkeley. ▼b Nuclear Engineering.
7730 ▼t Dissertation Abstracts International ▼g 80-01B(E).
773 ▼t Dissertation Abstract International
790 ▼a 0028
791 ▼a Ph.D.
792 ▼a 2018
793 ▼a English
85640 ▼u http://www.riss.kr/pdu/ddodLink.do?id=T14998344 ▼n KERIS
980 ▼a 201812 ▼f 2019
990 ▼a 관리자