CFD analýza proudění chladiv v jaderném reaktoru VVER440

Kód výsledku v 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>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

CFD analysis of coolant flow in the nuclear reactor VVER440

Popis výsledku v původním jazyce

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

Název v anglickém jazyce

CFD analysis of coolant flow in the nuclear reactor VVER440

Popis výsledku anglicky

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

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

<a href="/cs/project/1H-PK%2F61" target="_blank" >1H-PK/61: Aplikace CFD kódů pro výzkum proudění v jaderném reaktoru.</a><br>

Návaznosti

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

Rok uplatnění

2007

Kód důvěrnosti údajů

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

Název periodika

Applied andComputational Mechanics

ISSN

1802-680X

e-ISSN

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Svazek periodika

1

Číslo periodika v rámci svazku

2

Stát vydavatele periodika

CZ - Česká republika

Počet stran výsledku

8

Strana od-do

499-506

Kód UT WoS článku

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EID výsledku v databázi Scopus

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