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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
2023 ANS Annual Meeting
June 11–14, 2023
Indianapolis, IN|Marriott Indianapolis Downtown
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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Latest News
NRC advisors give nod to Hermes construction permit
Having completed its review of the construction permit application for Kairos Power’s Hermes test reactor early last month, the Nuclear Regulatory Commission’s Advisory Committee on Reactor Safeguards (ACRS) recently submitted its conclusions to the agency, recommending approval.
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.