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Measurement Challenges Associated With Irradiated Reactor Components

Published online by Cambridge University Press:  10 February 2011

Steven R. Doctor*
Affiliation:
Pacific Northwest National Laboratory, Engineering Mechanics, Measurement and NDE Group, Richland, WA, 99352
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Abstract

Nuclear reactor components are known to degrade as reactors age. The reactor pressure vessel and the reactor internals are subjected to the highest radiation fields and thus, age faster. Some boiling water reactors are experiencing extensive cracking of the core shroud and some pressurized water reactors are experiencing a reduction in their fracture toughness. This paper provides background information on reactor pressure vessel materials, fabrication, and construction practices. It identifies some of the challenges that are associated with the nondestructive measurement of changes in material properties associated with these components. The inspection environment, surface conditions and designs are also discussed.

Type
Research Article
Copyright
Copyright © Materials Research Society 1998

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References

REFERENCES

1. Doctor, S. R., Bush, S. H., Selby, G. P., Simonen, F. A., Taylor, T. T. in Eleventh Water Reactor Safety Research Information Meeting, U. S. Nuc. Reg. Comm., NUREG/CP-0048, Vol.4, pp. 4164 (1984).Google Scholar
2. Taylor, T. T.. Crawford, S. L., Doctor, S. R., Posakony, G. J., Detection of Small-Sized Near-Surface Under-clad Cracks in Reactor Pressure Vessels, U. S. Nuc. Reg. Comm., NUREG/CR-2878, PNL-4373, 1983.Google Scholar
3. Walker, S. M., BWR RPV Access/Inspection Activities at the EPRI NDE Center in Nondestructive Evaluation Research Progress in 1990: Proceedings from the Eleventh Annual EPRI NDE Information Meeting, NP-7047, Sec. 34, 1990.Google Scholar