東華大學圖書館 |

Language: English

Help

回圖書館首頁

手機版館藏查詢

Back

Switch To: Labeled | MARC Mode | ISBD

Methodology Development for High-to-...

Kulkarni, Nilay Atul,

Linked to FindBook

Google Book

Amazon

博客來

Methodology Development for High-to-Low Information of Subchannel Code CTF with CFD Code Nek5000 /

Record Type:	Electronic resources : Monograph/item
Title/Author:	Methodology Development for High-to-Low Information of Subchannel Code CTF with CFD Code Nek5000 // Nilay Atul Kulkarni.
Author:	Kulkarni, Nilay Atul,
Description:	1 electronic resource (69 pages)
Notes:	Source: Masters Abstracts International, Volume: 84-12.
Contained By:	Masters Abstracts International84-12.
Subject:	Friction. -
Online resource:	https://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=30463951
ISBN:	9798379659264

Methodology Development for High-to-Low Information of Subchannel Code CTF with CFD Code Nek5000 /
Kulkarni, Nilay Atul,

Methodology Development for High-to-Low Information of Subchannel Code CTF with CFD Code Nek5000 /Nilay Atul Kulkarni. - 1 electronic resource (69 pages)

Source: Masters Abstracts International, Volume: 84-12.

Precise thermal hydraulic analysis of reactor core is essential for safety and power analysis of a nuclear reactor. Complete reactor core calculations can be carried out using subchannel codes, but these codes often lack the resolution and fidelity to capture physical phenomenon occurring at smaller scales. Computational Fluid Dynamics (CFD) on the other hand can capture these phenomena but it is computationally expensive.The High-To-Low (Hi2Lo) model fidelity information seeks to bridge this gap by using data extracted from high-fidelity modeling and simulation (M&S) tools such as CFD codes and applying it as informing parameters to improve macroscopic physical phenomenon M&S in CTF. In this study, a methodology is developed to inform the subchannel code CTF with the spectral element code Nek5000. Subchannels are modeled with various spacer grids addressed in the PSBT benchmark and turbulent simulation are carried out using Large Eddy Simulation (LES) turbulence modelling. With these simulations the grid loss coefficient and the custom friction factor are calibrated to be informed to account for form and friction pressure loss in CTF. Friction factor calibration is carried out using friction velocity data obtained from different levels of mesh refinement over a range of flowrates and different levels of mesh refinement. With the friction factor calibration, an attempt is made to demonstrate the propagation of mesh-based uncertainty from high-fidelity Nek5000 to lower fidelity CTF.The presence of spacer grids not only causes form pressure loss but also causes augmentation in the turbulence locally which causes mixing between adjacent subchannels and affects the heat transfer from the fuel rods surface to the coolant. In this study, a center-center subchannel configuration with the simplified spacer grids is modeled to extract Hi2Lo data for a single-phase turbulent mixing multiplier and to calculate the enhanced heat transfer coefficient.

English

ISBN: 9798379659264Subjects--Topical Terms:

650299
Friction.

Methodology Development for High-to-Low Information of Subchannel Code CTF with CFD Code Nek5000 /
LDR:03502nmm a22004813i 4500 001 2430262
005 20250519115930.5
006 m o d
007 cr|nu||||||||
008 261011s2023 miu||||||m |||||||eng d
020 $a 9798379659264
035 $a (MiAaPQD)AAI30463951
035 $a (MiAaPQD)NCState_Univ18402040703
035 $a AAI30463951
040 $a MiAaPQD $b eng $c MiAaPQD $e rda
100 1 $a Kulkarni, Nilay Atul, $e author. $3 3818499
245 1 0 $a Methodology Development for High-to-Low Information of Subchannel Code CTF with CFD Code Nek5000 / $c Nilay Atul Kulkarni.
264 1 $a Ann Arbor : $b ProQuest Dissertations & Theses, $c 2023
300 $a 1 electronic resource (69 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: 84-12.
500 $a Advisors: Holler, David; Ivanov, Kostadin; Avramova, Maria.
502 $b M.Sc. $c North Carolina State University $d 2023.
520 $a Precise thermal hydraulic analysis of reactor core is essential for safety and power analysis of a nuclear reactor. Complete reactor core calculations can be carried out using subchannel codes, but these codes often lack the resolution and fidelity to capture physical phenomenon occurring at smaller scales. Computational Fluid Dynamics (CFD) on the other hand can capture these phenomena but it is computationally expensive.The High-To-Low (Hi2Lo) model fidelity information seeks to bridge this gap by using data extracted from high-fidelity modeling and simulation (M&S) tools such as CFD codes and applying it as informing parameters to improve macroscopic physical phenomenon M&S in CTF. In this study, a methodology is developed to inform the subchannel code CTF with the spectral element code Nek5000. Subchannels are modeled with various spacer grids addressed in the PSBT benchmark and turbulent simulation are carried out using Large Eddy Simulation (LES) turbulence modelling. With these simulations the grid loss coefficient and the custom friction factor are calibrated to be informed to account for form and friction pressure loss in CTF. Friction factor calibration is carried out using friction velocity data obtained from different levels of mesh refinement over a range of flowrates and different levels of mesh refinement. With the friction factor calibration, an attempt is made to demonstrate the propagation of mesh-based uncertainty from high-fidelity Nek5000 to lower fidelity CTF.The presence of spacer grids not only causes form pressure loss but also causes augmentation in the turbulence locally which causes mixing between adjacent subchannels and affects the heat transfer from the fuel rods surface to the coolant. In this study, a center-center subchannel configuration with the simplified spacer grids is modeled to extract Hi2Lo data for a single-phase turbulent mixing multiplier and to calculate the enhanced heat transfer coefficient.
546 $a English
590 $a School code: 0155
650 4 $a Friction. $3 650299
650 4 $a Heat transfer. $3 3391367
650 4 $a Nuclear energy. $3 539127
650 4 $a Partial differential equations. $3 2180177
650 4 $a Nuclear reactors. $3 673875
650 4 $a Viscosity. $3 1050706
650 4 $a Turbulence models. $3 3682363
650 4 $a Design. $3 518875
650 4 $a Nuclear engineering. $3 595435
650 4 $a Reynolds number. $3 3681436
650 4 $a Geometry. $3 517251
650 4 $a Energy. $3 876794
650 4 $a Fluid mechanics. $3 528155
650 4 $a Mathematics. $3 515831
650 4 $a Mechanics. $3 525881
650 4 $a Nuclear physics. $3 517741
650 4 $a Physics. $3 516296
650 4 $a Thermodynamics. $3 517304
690 $a 0389
690 $a 0552
690 $a 0791
690 $a 0204
690 $a 0405
690 $a 0346
690 $a 0756
690 $a 0605
690 $a 0348
710 2 $a North Carolina State University. $e degree granting institution. $3 3765716
720 1 $a Holler, David $e degree supervisor.
720 1 $a Ivanov, Kostadin $e degree supervisor.
720 1 $a Avramova, Maria $e degree supervisor.
773 0 $t Masters Abstracts International $g 84-12.
790 $a 0155
791 $a M.Sc.
792 $a 2023
856 4 0 $u https://pqdd.sinica.edu.tw/twdaoapp/servlet/advanced?query=30463951