東華大學圖書館 |

語系: 繁體中文

說明(常見問題)

回圖書館首頁

手機版館藏查詢

登入

回首頁

切換: 標籤 | MARC模式 | ISBD

Experimental and Computational Inves...

Hughes, Joel Thomas.

FindBook

Google Book

Amazon

博客來

Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-Cooled High-Temperature Reactors.

紀錄類型:	書目-電子資源 : Monograph/item
正題名/作者:	Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-Cooled High-Temperature Reactors./
作者:	Hughes, Joel Thomas.
出版者:	Ann Arbor : ProQuest Dissertations & Theses, : 2017,
面頁冊數:	280 p.
附註:	Source: Dissertation Abstracts International, Volume: 79-01(E), Section: B.
Contained By:	Dissertation Abstracts International79-01B(E).
標題:	Nuclear engineering. -
電子資源:	http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=10269796
ISBN:	9780355150070

Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-Cooled High-Temperature Reactors.
Hughes, Joel Thomas.

Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-Cooled High-Temperature Reactors. - Ann Arbor : ProQuest Dissertations & Theses, 2017 - 280 p.

Source: Dissertation Abstracts International, Volume: 79-01(E), Section: B.

Thesis (Ph.D.)--The University of New Mexico, 2017.

Fluoride salt-cooled high-temperature reactors (FHRs) face a number of challenges similar to those faced by other Generation IV advanced reactor concepts. Predicting heat transfer in these systems accurately and reliably is one major challenge. Another is ensuring the safety of these systems during challenging operating conditions across the design basis envelope. Finally, achieving good economics to compete in a modern power generation portfolio is necessary for moving any nuclear power plant concept past the pre-conceptual stage. This dissertation attempts to support, from a thermal-hydraulics research standpoint, the case that the FHR can attain these goals. The dissertation focuses on several aspects of the design. The common thread through the different studies is ultimately rooted in improving plant safety and economics.

ISBN: 9780355150070Subjects--Topical Terms:

595435
Nuclear engineering.

Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-Cooled High-Temperature Reactors.
LDR:02926nmm a2200313 4500 001 2162985
005 20181022104648.5
008 190424s2017 ||||||||||||||||| ||eng d
020 $a 9780355150070
035 $a (MiAaPQ)AAI10269796
035 $a (MiAaPQ)newmex:11745
035 $a AAI10269796
040 $a MiAaPQ $c MiAaPQ
100 1 $a Hughes, Joel Thomas. $3 3350987
245 1 0 $a Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-Cooled High-Temperature Reactors.
260 1 $a Ann Arbor : $b ProQuest Dissertations & Theses, $c 2017
300 $a 280 p.
500 $a Source: Dissertation Abstracts International, Volume: 79-01(E), Section: B.
500 $a Adviser: Edward Blandford.
502 $a Thesis (Ph.D.)--The University of New Mexico, 2017.
520 $a Fluoride salt-cooled high-temperature reactors (FHRs) face a number of challenges similar to those faced by other Generation IV advanced reactor concepts. Predicting heat transfer in these systems accurately and reliably is one major challenge. Another is ensuring the safety of these systems during challenging operating conditions across the design basis envelope. Finally, achieving good economics to compete in a modern power generation portfolio is necessary for moving any nuclear power plant concept past the pre-conceptual stage. This dissertation attempts to support, from a thermal-hydraulics research standpoint, the case that the FHR can attain these goals. The dissertation focuses on several aspects of the design. The common thread through the different studies is ultimately rooted in improving plant safety and economics.
520 $a This dissertation has four major contributions in support of the FHR: experimental investigation of a directional direct reactor auxiliary cooling system (DRACS) heat exchanger (DHX), experimental investigation of twisted versus plain tube heat transfer for molten salt heat exchangers, and two computational studies, one on DRACS reliability and one on heat exchanger optimization. The results for the four studies are presented and discussed. The directional DHX study was performed using a hydrodynamic experimental setup with water as a working fluid and heat transfer performance inferred. The experimental heat transfer work was performed using a simulant fluid, Dowtherm A, to match the important non-dimensional heat transfer parameters. The computational DRACS reliability study was performed using MATLAB and RELAP5-3D, and the computational heat exchanger optimization study was performed using Python and available metaheuristic algorithms. The implications of the various studies are tied together in the conclusions section, with suggestions for future work.
590 $a School code: 0142.
650 4 $a Nuclear engineering. $3 595435
650 4 $a Engineering. $3 586835
690 $a 0552
690 $a 0537
710 2 $a The University of New Mexico. $b Nuclear Engineering. $3 3350988
773 0 $t Dissertation Abstracts International $g 79-01B(E).
790 $a 0142
791 $a Ph.D.
792 $a 2017
793 $a English
856 4 0 $u http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=10269796