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171305

Transient Thermal Performance of a Single Cooling Channel in a PWR Reactor Core.

Article

Last updated: 22 Jan 2023

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Subjects

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Tags

Mechanical Power Engineering

Abstract

The objective of this paper is to investigate the transient thermal performance of a single cooling channel in a pressurized water reactor (PWR). A new developed two dimensional fuel rod code in which the radial and axial heat transfer are taken into consideration is used for calculation. This code is used to study the steady-state and transient temperature behaviour of nuclear fuel rods in light water reactors. In addition, the real thermodynamic conditions as the variation of the coolant heat transfer coefficient along the channel length and the gap thermal resistance- are taken into consideration. These real thermodynamic properties of the coolant are calculated using VDI correlations.  

DOI

10.21608/bfemu.2021.171305

Authors

First Name

Mohamed

Last Name

Ahmed Mahgoub

MiddleName

Mahmoud

Affiliation

Associate Professor., Mechanical Power Engineering Department., Faculty of Engineering., El-Mansoura University., Mansoura., Egypt.

Email

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City

Mansoura

Orcid

-

Volume

15

Article Issue

2

Related Issue

24852

Issue Date

1990-12-01

Receive Date

1990-10-11

Publish Date

2021-05-22

Page Start

69

Page End

77

Print ISSN

1110-0923

Online ISSN

2735-4202

Article File

BFEMU_Volume 15_Issue 2_Pages 69-77.pdf

PDF . 122.3kB

Link

https://bfemu.journals.ekb.eg/article_171305.html

Detail API

https://bfemu.journals.ekb.eg/service?article_code=171305

Order

19

Type

Research Studies

Type Code

1,205

Publication Type

Journal

Publication Title

MEJ. Mansoura Engineering Journal

Publication Link

https://bfemu.journals.ekb.eg/

MainTitle

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Details

Type

Article

Created At

22 Jan 2023