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Modeling, Simulation and Optimization of Lead-Cooled Fast Reactors.

Record Type:	Electronic resources : Monograph/item
Title/Author:	Modeling, Simulation and Optimization of Lead-Cooled Fast Reactors./
Author:	Al-Dawood, Khaldoon Ali Mohammad.
Description:	1 online resource (89 pages)
Notes:	Source: Masters Abstracts International, Volume: 83-05.
Contained By:	Masters Abstracts International83-05.
Subject:	Design specifications. -
Online resource:	http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=28747769click for full text (PQDT)
ISBN:	9798494445919

Modeling, Simulation and Optimization of Lead-Cooled Fast Reactors.
Al-Dawood, Khaldoon Ali Mohammad.

Modeling, Simulation and Optimization of Lead-Cooled Fast Reactors. - 1 online resource (89 pages)

Source: Masters Abstracts International, Volume: 83-05.

Thesis (M.Sc.)--North Carolina State University, 2021.

Includes bibliographical references

The last two decades witnessed an increasing interest in Liquid Metal-cooled Fast Reactor (LMFR) technology. This was associated with the establishment of the Generation IV International Forum (GIF) in 2001. Sodium-cooled Fast Reactors (SFRs) have traditionally received the majority of the attention. Lead-Cooled Fast Reactor (LFR) technology has recently gained more momentum in research and development. This is due to the neutronic, chemical and thermal advantages that lead coolant has that potentially enables safer and more economical plant designs.The computer code LUPINE has been developed at North Carolina State University for the modeling and simulation of LMFRs. The code performs coupled neutronics, thermal hydraulics and thermal expansion calculations. In the first part of this thesis, the capabilities of LUPINE have been extended to enable the modeling and simulation of LFRs. These capabilities include the neutronic and thermal models of lead coolant, gap region model and thermal models of uranium mononitride (UN) fuel. The theory of implementing these capabilities in LUPINE has been presented.The second part of this research investigates the optimization of LMFR designs. To do this, a new general purpose Design and Optimization Methodology (DOM) has been developed. The theory behind this methodology is presented and a Python program was developed to automate the application. The method was applied to the Westinghouse Electric Company LLC (WEC) long-life core LFR with the goal of coming up with a better economically performing core. An optimized core was developed that decreased the Levelized Cost Of Electricity (LCOE) by 2.56 [%], which is a cost savings of 17, 765, 685 [$] over the life of the plant.

Electronic reproduction.
Ann Arbor, Mich. :
ProQuest,
2023

Mode of access: World Wide Web

ISBN: 9798494445919Subjects--Topical Terms:

3683440
Design specifications.
Index Terms--Genre/Form:

542853
Electronic books.

Modeling, Simulation and Optimization of Lead-Cooled Fast Reactors.
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035 $a AAI28747769
040 $a MiAaPQ $b eng $c MiAaPQ $d NTU
100 1 $a Al-Dawood, Khaldoon Ali Mohammad. $3 3694402
245 1 0 $a Modeling, Simulation and Optimization of Lead-Cooled Fast Reactors.
264 0 $c 2021
300 $a 1 online resource (89 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: Masters Abstracts International, Volume: 83-05.
500 $a Advisor: Kropaczek, David; Azmy, Yousry; Palmtag, Scott.
502 $a Thesis (M.Sc.)--North Carolina State University, 2021.
504 $a Includes bibliographical references
520 $a The last two decades witnessed an increasing interest in Liquid Metal-cooled Fast Reactor (LMFR) technology. This was associated with the establishment of the Generation IV International Forum (GIF) in 2001. Sodium-cooled Fast Reactors (SFRs) have traditionally received the majority of the attention. Lead-Cooled Fast Reactor (LFR) technology has recently gained more momentum in research and development. This is due to the neutronic, chemical and thermal advantages that lead coolant has that potentially enables safer and more economical plant designs.The computer code LUPINE has been developed at North Carolina State University for the modeling and simulation of LMFRs. The code performs coupled neutronics, thermal hydraulics and thermal expansion calculations. In the first part of this thesis, the capabilities of LUPINE have been extended to enable the modeling and simulation of LFRs. These capabilities include the neutronic and thermal models of lead coolant, gap region model and thermal models of uranium mononitride (UN) fuel. The theory of implementing these capabilities in LUPINE has been presented.The second part of this research investigates the optimization of LMFR designs. To do this, a new general purpose Design and Optimization Methodology (DOM) has been developed. The theory behind this methodology is presented and a Python program was developed to automate the application. The method was applied to the Westinghouse Electric Company LLC (WEC) long-life core LFR with the goal of coming up with a better economically performing core. An optimized core was developed that decreased the Levelized Cost Of Electricity (LCOE) by 2.56 [%], which is a cost savings of 17, 765, 685 [$] over the life of the plant.
533 $a Electronic reproduction. $b Ann Arbor, Mich. : $c ProQuest, $d 2023
538 $a Mode of access: World Wide Web
650 4 $a Design specifications. $3 3683440
650 4 $a Nuclear reactors. $3 673875
650 4 $a Viscosity. $3 1050706
650 4 $a Research & development--R&D. $3 3554335
650 4 $a Heat conductivity. $3 3681489
650 4 $a Sodium. $3 3562677
650 4 $a Optimization. $3 891104
650 4 $a Atmospheric pressure. $3 3686417
650 4 $a Atmospheric sciences. $3 3168354
650 4 $a Eigenvalues. $3 631789
655 7 $a Electronic books. $2 lcsh $3 542853
690 $a 0725
710 2 $a ProQuest Information and Learning Co. $3 783688
710 2 $a North Carolina State University. $3 1018772
773 0 $t Masters Abstracts International $g 83-05.
856 4 0 $u http://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=28747769 $z click for full text (PQDT)