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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Nicholas Tsoulfanidis—ANS member since 1969
As an undergraduate I studied physics at the University of Athens. I entered the university in 1955 after successfully passing a national exam (came up fourth in a field of about 700 candidates). Upon graduation and finishing my mandatory two-year military service, the plan was to teach physics either in a public high school or as a tutor for a private for-profit institution, preparing high school students for the national exam.
C. J. Kiger, C. D. Sexton, H. M. Hashemian, R. D. O’Hagan, L. Dormann, W. Wasfy
Nuclear Technology | Volume 200 | Number 2 | November 2017 | Pages 93-105
Technical Paper | doi.org/10.1080/00295450.2017.1360716
Articles are hosted by Taylor and Francis Online.
This paper reports the results of in situ cable testing performed at the Oyster Creek Nuclear Generating Station in September 2016 to assess the aging condition of a number of cables as installed in the plant. Despite having been in service for over 40 years, our results found that these cables still met their qualification criteria, were in good working condition, and could continue to serve the plant for the foreseeable future. Some degradation in the cable insulation was noted but not as much as one would expect after more than 40 years of service in a nuclear power plant. Specifically, test results revealed that 10% of cables exhibited a noticeable degree of degradation, 30% were only slightly degraded, and the remaining 60% were essentially unaffected by aging. In the case of jacketed cables, which were assessed using walkdowns performed by the plant’s personnel, almost all aging and degradation were limited to the jacket material while the underlying cable insulation was largely unaffected. This is consistent with laboratory test results, which have shown that jacket material, especially Neoprene and Hypalon, degrade much faster than cross-linked polyethylene (XLPE) and other materials that are used for primary cable insulation.