Detail publikace

CFD Analýza termo-hydraulických parametru nukleárního reaktoru.

KATOLICKÝ, J. JÍCHA, M. FRÉLICH, J.

Originální název

CFD ANALYSIS OF NUCLEAR REACTOR THERMAL-HYDRAULICS WITH EXPERIMENTAL VALIDATION OF REACTOR VESSEL HEAD COOL-DOWN UNDER NATURAL CIRCULATION CONDITIONS

Český název

CFD Analýza termo-hydraulických parametru nukleárního reaktoru.

Anglický název

CFD ANALYSIS OF NUCLEAR REACTOR THERMAL-HYDRAULICS WITH EXPERIMENTAL VALIDATION OF REACTOR VESSEL HEAD COOL-DOWN UNDER NATURAL CIRCULATION CONDITIONS

Typ

článek ve sborníku

Jazyk

en

Originální abstrakt

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 regime, several calculations were performed for various number of the reactor coolant system (RCS) loops connected 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 coolant flow rate at the core outlet on the heat transfer from the under-head space.

Český abstrakt

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 regime, several calculations were performed for various number of the reactor coolant system (RCS) loops connected 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 coolant flow rate at the core outlet on the heat transfer from the under-head space.

Anglický abstrakt

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 regime, several calculations were performed for various number of the reactor coolant system (RCS) loops connected 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 coolant flow rate at the core outlet on the heat transfer from the under-head space.

Rok RIV

2006

Vydáno

13.08.2006

Místo

Sydney, Australie

Strany od

20

Strany do

29

Strany počet

9

BibTex


@inproceedings{BUT20084,
  author="Jaroslav {Katolický} and Miroslav {Jícha} and Jan {Frélich}",
  title="CFD ANALYSIS OF NUCLEAR REACTOR THERMAL-HYDRAULICS WITH EXPERIMENTAL VALIDATION OF REACTOR VESSEL HEAD COOL-DOWN UNDER NATURAL CIRCULATION CONDITIONS",
  annote="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 regime, several calculations were performed for various number of the reactor coolant system (RCS) loops connected 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 coolant flow rate at the core outlet on the heat transfer from the under-head space. 
",
  booktitle="13th INTERNATIONAL HEAT TRANSFER CONFERENCE",
  chapter="20084",
  year="2006",
  month="august",
  pages="20--29",
  type="conference paper"
}