Published 1991 | Version v1
Book

Thermal stratification in nuclear reactor piping system

  • 1. Electric Power Research Inst., Palo Alto, CA (United States)

Description

Thermal stratification, cycling, and striping (TASCS) issue has drawn attention recently because of the incidents at several nuclear plants relative to thermal fatigue in piping systems connected to the main coolant piping. U.S. nuclear utilities are addressing the issue in response to the concerns. In particular, the Electric Power Research Institute (EPRI) initiated a major research program to resolve the TASCS issue. In Phase 1 research, a methodology and program have been developed to conduct detailed research into mechanisms which lead to fatigue in nominally stagnant piping systems near the reactor coolant piping. Three key efforts from the Phase 1 program are described in this paper. First, the line evaluation methodology is described, which also leads to requirements for the Phase 2 program. Second, tests to investigate interaction between main coolant piping and stagnant attached lines by turbulence penetration are described. Turbulence penetration into unisolable lines, or the transport of turbulence into stagnant piping from the reactor coolant system (RCS) line, represents a mechanism for carrying hot RCS water into regions filled with colder water. The possibility of stratification of the two fluids (and the resultant stresses) are the reason for developing an understanding of the turbulence penetration process. Lastly, results of an evaluation to develop a loading definition for thermal striping are included. Future plans and prospective results are also discussed. (author)

Additional details

Publishing Information

Publisher
Japan Society of Mechanical Engineers.
Imprint Place
Tokyo (Japan)
Imprint Title
The 1st JSME/ASME joint international conference on nuclear engineering
Imprint Pagination
1273 p.
Journal Page Range
v. 2 p. 235-241.

Conference

Title
1. JSME/ASME joint international conference on nuclear engineering.
Dates
4-7 Nov 1991.
Place
Tokyo (Japan).

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
23075730
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
FLOW RATE; MOCKUP; PIPES; REACTOR COOLING SYSTEMS; SIMULATION; STRATIFICATION; THERMAL CYCLING; THERMAL FATIGUE; TURBULENT FLOW; TWO-PHASE FLOW; VELOCITY
Descriptors DEC
COOLING SYSTEMS; FATIGUE; FLUID FLOW; MECHANICAL PROPERTIES; REACTOR COMPONENTS; STRUCTURAL MODELS

Optional Information

Notes
Imprint:Composed of two volumes.