Published October 1998 | Version v1
Miscellaneous

Numerical analysis of thermally stratified flow in the pressurizer surge line

  • 1. KINS, Taejon (Korea, Republic of)
  • 2. KAERI, Taejon (Korea, Republic of)

Description

Thermal stratification in the pressurizer surge line of pressurized water reactor has been known to cause considerable local thermal stress and global bending stress in the surge line piping, which may consequently threat the integrity of the piping. Thus the assessment of the potential for piping damage due to the thermal stratification-induced stresses has become one of the major safety issues. To obtain reliable results of stress evaluation, it is necessary to determine as accurately and realistically as possible the transient temperature distribution in the wall of the piping in which thermally stratified flow occurs. This paper presents an effective numerical method for simulating the transient behavior of thermally stratified flow and temperature distributions in the pressurizer surge line piping using the finite volume. The method presented in this paper employs a body-fitted, non-orthogonal grid system to accommodate the piping wall of circular geometry and the interface of the two fluids at different temperatures, of which the level is variable. As an illustration, the present method was applied to calculate the thermally stratified flow and temperature distribution in the piping of a typical pressurizer surge line. For verifying the effectiveness of the method, the result was compared with available analytical steady-state solution. In addition, this study investigates the effects of level of the interface between two thermally stratified fluids on the transient temperature distribution in the piping

Part of:
Proceedings of the Korean Nuclear Society autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the Korean Nuclear Society autumn meeting
Imprint Pagination
[CD-ROM]
Journal Page Range
[6 p.]

Conference

Title
1998 autumn meeting of the Korean Nuclear Society
Dates
30-31 Oct 1998
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
32066980
Subject category
S42: ENGINEERING;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
FLUID FLOW; GEOMETRY; NUMERICAL ANALYSIS; PIPES; PWR TYPE REACTORS; STRATIFICATION; SURGES; THERMAL ANALYSIS
Descriptors DEC
ENRICHED URANIUM REACTORS; MATHEMATICS; POWER REACTORS; REACTORS; THERMAL REACTORS; TUBES; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
11 refs, 10 figs