Published 2003 | Version v1
Miscellaneous

Thermal stratification phenomenon in a branch piping with in-leakage

  • 1. Korea Power Engineering Company, Daejon (Korea, Republic of)
  • 2. KAIST, Daejon (Korea, Republic of)

Description

A numerical analysis was performed to estimate thermal stratification phenomenon in the branch piping of nuclear power plant. Due to the turbulent penetration force by the flow in reactor coolant system piping without the valve leak, thermal stratification in the branch piping can be generated if the location of the first valve is greater than that of turbulent penetration. Even though the location of the first valve is less than that of turbulent penetration, thermal stratification can be generated by valve leak. The maximum temperature difference between top and bottom of the horizontal piping was evaluated to be about 185K when the valve leakage is about 10 times as large as the allowable value. The thermal stratification effect of the branch piping was decreased by forced convection of leak flow, however, when the valve leakage is increased to about 15 times the allowable value. Because the temperature difference depends on a number of factors such as piping layout, diameter, leak location, and wall thickness, it is recommended that specific analysis should be conducted to estimate the thermal stratification effect by valve leakage

Part of:
Proceedings of the tenth international topical meeting on nuclear reactor thermal hydraulics

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
Proceedings of the tenth international topical meeting on nuclear reactor thermal hydraulics
Imprint Pagination
[1 CD-ROM]
Journal Page Range
[8 p.]

Conference

Title
NURETH-10
Dates
5-11 Oct 2003
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36067446
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
LEAKS; NUCLEAR POWER PLANTS; PIPES; REACTOR COOLING SYSTEMS; STRATIFICATION; TURBULENCE; VALVES
Descriptors DEC
CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY SYSTEMS; EQUIPMENT; FLOW REGULATORS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; THERMAL POWER PLANTS; TUBES

Optional Information

Notes
15 refs, 8 figs