Temperature distributions in well-insulated and closed/nearly closed-ended vertical pipes

Conference · Sun Jan 01 04:00:00 EST 1989 · Transactions of the American Nuclear Society; (USA)

OSTI ID:6852607

Coffield, R D; Antaki, G A

Many different sized auxiliary lines are tied into the primary heat transport system piping of nuclear reactors and other similar types of systems. Often these lines are valve closed so that the contained fluid is either stagnant or flowing at low velocity due to free convection or small amounts of leakage (across valves). The characterization of the axial temperature distributions in these lines is important because of potential structural consequences to the pipe. For example, in addition to being required for determining basic thermal expansion allowances in piping networks, it is needed relative to other considerations such as thermal fatigue, which could occur due to leakage attaining a different temperature than that of the trunk line that it flows into. As would be anticipated, conditions that result in larger fluid temperature differences at a particular network juncture generally result in the more severe structural impact (e.g., thermal stratification/striping assessments become necessary). The purpose of this paper was to characterize some of the major phenomena that needed to be considered relative to predicting the range of temperature variations that can be experienced in the piping. The major emphases of these discussions are on vertical pipe orientation (either up or down).

• OSTI ID: 6852607
• Report Number(s): CONF-890604--
• Conference Information: Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 59
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
CONVECTION
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FATIGUE
FLOW RATE
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LEAKS
MASS TRANSFER
MATHEMATICAL MODELS
MECHANICAL PROPERTIES
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PIPES
POWER PLANTS
PRIMARY COOLANT CIRCUITS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
STRATIFICATION
TEMPERATURE GRADIENTS
THERMAL POWER PLANTS