CFD analysis of coolant flow in the nuclear reactor VVER440

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216305%3A26210%2F07%3APU69731" target="_blank" >RIV/00216305:26210/07:PU69731 - isvavai.cz</a>

Result on the web

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DOI - Digital Object Identifier

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Result language

angličtina

Original language name

CFD analysis of coolant flow in the nuclear reactor VVER440

Original language description

The paper introduces results of computational fluid dynamics (CFD) simulations of water flow at the reactor pressure vessel (RPV) outlet and under the RPV head. Several CFD calculations of the steady-state and dynamic processes involving forced and natural circulation of coolant are presented in the paper. In the steady-state re-gime, several calculations were performed for various number of the reactor coolant system (RCS) loops con-nected to the reactor and the results have been used to analyse the effect of the RCS configuration to the coolant flow at the reactor outlet and under the reactor vessel head. General flow patterns are described in the outlet part of the reactor and under the reactor vessel head and, also, the influence of a lower flow rate through the reactor on thermal homogeneity of coolant under the vessel head. Simultaneously, we discuss the influence of the cool-ant flow rate at the core outlet on the heat transfer from the under-head space. Unsteady calculation was

Czech name

CFD analýza proudění chladiv v jaderném reaktoru VVER440

Czech description

The paper introduces results of computational fluid dynamics (CFD) simulations of water flow at the reactor pressure vessel (RPV) outlet and under the RPV head. Several CFD calculations of the steady-state and dynamic processes involving forced and natural circulation of coolant are presented in the paper. In the steady-state re-gime, several calculations were performed for various number of the reactor coolant system (RCS) loops con-nected to the reactor and the results have been used to analyse the effect of the RCS configuration to the coolant flow at the reactor outlet and under the reactor vessel head. General flow patterns are described in the outlet part of the reactor and under the reactor vessel head and, also, the influence of a lower flow rate through the reactor on thermal homogeneity of coolant under the vessel head. Simultaneously, we discuss the influence of the cool-ant flow rate at the core outlet on the heat transfer from the under-head space. Unsteady calculation was

Type

J_x - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)

CEP classification

JF - Nuclear energy

OECD FORD branch

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Project

<a href="/en/project/1H-PK%2F61" target="_blank" >1H-PK/61: Application of CFD codes ion research of fluid behavior of nuclear reactor.</a><br>

Continuities

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year

2007

Confidentiality

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Name of the periodical

Applied andComputational Mechanics

ISSN

1802-680X

e-ISSN

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Volume of the periodical

1

Issue of the periodical within the volume

2

Country of publishing house

CZ - CZECH REPUBLIC

Number of pages

8

Pages from-to

499-506

UT code for WoS article

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EID of the result in the Scopus database

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