| LDR | | 02662nam u200421 4500 |
| 001 | | 000000422023 |
| 005 | | 20190215165807 |
| 008 | | 181129s2018 |||||||||||||||||c||eng d |
| 020 | |
▼a 9780438127098 |
| 035 | |
▼a (MiAaPQ)AAI10903103 |
| 035 | |
▼a (MiAaPQ)umichrackham:001298 |
| 040 | |
▼a MiAaPQ
▼c MiAaPQ
▼d 247004 |
| 082 | 0 |
▼a 539.76 |
| 100 | 1 |
▼a Chen, Minghui. |
| 245 | 10 |
▼a Performance Testing and Modeling of Printed Circuit Heat Exchangers for Advanced Nuclear Reactor Applications. |
| 260 | |
▼a [S.l.]:
▼b University of Michigan.,
▼c 2018. |
| 260 | 1 |
▼a Ann Arbor:
▼b ProQuest Dissertations & Theses,
▼c 2018. |
| 300 | |
▼a 219 p. |
| 500 | |
▼a Source: Dissertation Abstracts International, Volume: 79-12(E), Section: B. |
| 500 | |
▼a Adviser: Xiaodong Sun. |
| 502 | 1 |
▼a Thesis (Ph.D.)--University of Michigan, 2018. |
| 520 | |
▼a The primary mission of very-high-temperature reactors (VHTRs) is to generate electricity and provide high-temperature process heat for industrial applications with high efficiency, which relies on an effective intermediate heat exchanger (IHX) t |
| 520 | |
▼a In this study, the thermal-hydraulic performance of a fabricated zigzag-channel PCHE was investigated. New pressure drop and heat transfer correlations were developed based on the experimental data. Local thermal-hydraulic performance of the PCH |
| 520 | |
▼a Furthermore, a computer code was developed to predict both the steady-state and transient behaviors of both straight-channel and zigzag-channel PCHEs. Comparisons of the numerical results with the experimental data indicated that the dynamic mod |
| 520 | |
▼a Finally, the heat exchanger model was implemented into a system dynamic code to simulate the transient behavior of a 20-MWth Fluoride-salt-cooled High-temperature Reactor (FHR). Results were obtained for three initiating events: a positive react |
| 520 | |
▼a This study provides critical insights into the thermal-hydraulic performance of PCHEs that can be applied to nuclear power, offshore industry, solar power, dual cycles for process heat applications, and cooling of electronics and fuel cells. |
| 590 | |
▼a School code: 0127. |
| 650 | 4 |
▼a Nuclear engineering. |
| 690 | |
▼a 0552 |
| 710 | 20 |
▼a University of Michigan.
▼b Nuclear Engineering & Radiological Sciences. |
| 773 | 0 |
▼t Dissertation Abstracts International
▼g 79-12B(E). |
| 773 | |
▼t Dissertation Abstract International |
| 790 | |
▼a 0127 |
| 791 | |
▼a Ph.D. |
| 792 | |
▼a 2018 |
| 793 | |
▼a English |
| 856 | 40 |
▼u http://www.riss.kr/pdu/ddodLink.do?id=T15000597
▼n KERIS
▼z 이 자료의 원문은 한국교육학술정보원에서 제공합니다. |
| 980 | |
▼a 201812
▼f 2019 |
| 990 | |
▼a ***1012033 |