Publication detail

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

KATOLICKÝ, J. JÍCHA, M. FRÉLICH, J.

Original Title

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

English Title

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

Type

conference paper

Language

en

Original Abstract

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.

English abstract

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.

Keywords

nuclear reactor

RIV year

2006

Released

13.08.2006

Location

Sydney, Australie

Pages from

20

Pages to

29

Pages count

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"
}