國立虎尾科技大學 |

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

Record Type:	Language materials, manuscript : Monograph/item
Title/Author:	Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-Cooled High-Temperature Reactors./
Author:	Hughes, Joel Thomas.
Description:	1 online resource (280 pages)
Notes:	Source: Dissertation Abstracts International, Volume: 79-01(E), Section: B.
Contained By:	Dissertation Abstracts International79-01B(E).
Subject:	Nuclear engineering. -
Online resource:	click for full text (PQDT)
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. - 1 online resource (280 pages)

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

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

Includes bibliographical references

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.

Electronic reproduction.
Ann Arbor, Mich. :
ProQuest,
2018

Mode of access: World Wide Web

ISBN: 9780355150070Subjects--Topical Terms:

655622
Nuclear engineering.
Index Terms--Genre/Form:

554714
Electronic books.

Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-Cooled High-Temperature Reactors.
LDR:03209ntm a2200349Ki 4500 001 917502
005 20181022104648.5
006 m o u
007 cr mn||||a|a||
008 190606s2017 xx obm 000 0 eng d
020 $a 9780355150070
035 $a (MiAaPQ)AAI10269796
035 $a (MiAaPQ)newmex:11745
035 $a AAI10269796
040 $a MiAaPQ $b eng $c MiAaPQ $d NTU
100 1 $a Hughes, Joel Thomas. $3 1191573
245 1 0 $a Experimental and Computational Investigations of Heat Transfer Systems in Fluoride Salt-Cooled High-Temperature Reactors.
264 0 $c 2017
300 $a 1 online resource (280 pages)
336 $a text $b txt $2 rdacontent
337 $a computer $b c $2 rdamedia
338 $a online resource $b cr $2 rdacarrier
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.
504 $a Includes bibliographical references
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.
533 $a Electronic reproduction. $b Ann Arbor, Mich. : $c ProQuest, $d 2018
538 $a Mode of access: World Wide Web
650 4 $a Nuclear engineering. $3 655622
650 4 $a Engineering. $3 561152
655 7 $a Electronic books. $2 local $3 554714
690 $a 0552
690 $a 0537
710 2 $a ProQuest Information and Learning Co. $3 1178819
710 2 $a The University of New Mexico. $b Nuclear Engineering. $3 1191574
773 0 $t Dissertation Abstracts International $g 79-01B(E).
856 4 0 $u http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=10269796 $z click for full text (PQDT)