STRESS ANALYSIS OF BELLOWS FOR THE HNPF INTERMEDIATE HEAT EXCHANGER

Technical Report · Sun Apr 15 04:00:00 EST 1962

DOI:https://doi.org/10.2172/4818729· OSTI ID:4818729

Chipman, R; Galantine, R; Susnir, J

A combined theoretical and experimental stress analysis was performed on a bellows to determine if it was suitable for use in absorbing the differential expansion between the shell and tubes of the intermediate heat exchanger for the Hallam Nuclear Power Facility (HNPF). Modes of deformation imposed, singly and in combination, upon a prototype bellows at room temperature included axial deflection, lateral deflection, angular rotation, torsional rotation, and pressurization. Good agreement was obtained between predicted and observed strains. All subsequent tests were performed with Na at 75 psig and 1000 deg F inside the bellows. During the first series of these tests, which simulated the cycling effects of 20 years of normal reactor operation, negligible damage occurred in the bellows. The second series of tests, with Na at 75 psig and 1000 deg F, showed that the bellows could withstand the large axial deflections which might occur during abnormal conditions involving failure of a pump in either the primary or secondary cooling system. In the final series of tests, the axial deflection stroke was gradually increased in a deliberate attempt to induce failure in the bellows. When the stroke was increased to approximately 30 times that expected during normal operation, a reproducible signal was obtained indicating that Na had leaked through the inner ply of the double-ply wall. Even at that time, there was no leakage of Na through the outer ply and the bellows still remained functional. It was concluded that the bellows is well suited for application in the HNPF intermediate heat exchanger. (auth)

• Research Organization: Atomic International. Div. of North American Aviation, Inc., Canoga Park, Calif.
• DOE Contract Number: AT(11-1)-GEN-8
• NSA Number: NSA-16-018660
• OSTI ID: 4818729
• Report Number(s): NAA-SR-4534
• Country of Publication: United States
• Language: English

Related Subjects

COOLANT LOOPS
DEFORMATION
EQUATIONS
EXPANSION
FAILURES
HEAT EXCHANGERS
HEAT TREATMENTS
HIGH TEMPERATURE
LABORATORY EQUIPMENT
LEAKS
LIQUID METAL COOLANT
MEASURED VALUES
POWER PLANTS
PRESSURE
PUMPS
REACTOR TECHNOLOGY
REACTORS
SHELLS
STRESSES
TESTING
TUBES
WIND