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Spectra Thermal Fatigue Tests Under Frequency Controlled Fluid Temperature Variation: Development of Test Equipment and Preliminary Tests

[+] Author Affiliations
Naoto Kasahara, Shinichi Hasebe, Sumio Kobaysashi, Masanori Ando, Nobuchika Kawasaki

Japan Nuclear Cycle Development Institute, Oarai, Ibaraki, Japan

Hiroshi Morita

Hitachi, Ltd., Hitachi-shi, Ibaraki, Japan

Paper No. PVP2004-2996, pp. 229-236; 8 pages
  • ASME/JSME 2004 Pressure Vessels and Piping Conference
  • Elevated Temperature Design and Analysis, Nonlinear Analysis, and Plastic Components
  • San Diego, California, USA, July 25–29, 2004
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4667-9
  • Copyright © 2004 by ASME


High cycle thermal fatigue induced by fluid temperature fluctuation is one of the important issues in nuclear plants. JNC has proposed a fatigue evaluation method paying attention to temperature attenuation related with frequency of fluctuation. In order to clarify the frequency effect of fluid temperature fluctuation on the crack initiation and propagation, a sodium temperature controlled thermal fatigue test equipment (SPECTRA) was developed. This equipment is capable of preciously controlling sodium temperature variation under various frequencies with a constant flow rate. This performance was achieved by the control of electromagnetic pumps without mechanical valve operations. Specimens are long straight pipes where temperature fluctuation ranges gradually reduce from upstream to downstream. As preliminary tests, temperature measurement and fatigue experiments were conducted. Measured temperature was preciously controlled under various frequencies. Cracks were observed in upstream area of a specimen. From above results, capability of frequency controlled test by SPECTRA facility was confirmed.

Copyright © 2004 by ASME



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