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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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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Deep Space: The new frontier of radiation controls
In commercial nuclear power, there has always been a deliberate tension between the regulator and the utility owner. The regulator fundamentally exists to protect the worker, and the utility, to make a profit. It is a win-win balance.
From the U.S. nuclear industry has emerged a brilliantly successful occupational nuclear safety record—largely the result of an ALARA (as low as reasonably achievable) process that has driven exposure rates down to what only a decade ago would have been considered unthinkable. In the U.S. nuclear industry, the system has accomplished an excellent, nearly seamless process that succeeds to the benefit of both employee and utility owner.
B. Mukherjee, M. H. El Haddad, M. L. Vanderglas, D. V. Leemans
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 505-512
Technical Paper | Materials | doi.org/10.13182/NT55-505
Articles are hosted by Taylor and Francis Online.
A large number of Monel 400 steam generator tubes may be subjected to low cycle fatigue because of the particular location of the thermal plate. A low cycle fatigue analysis method, simulating the deformation response of structural component elements due to irregular load history, was applied to predict stress-strain behavior and then fatigue life of the Monel 400 steam generator tubing. The experiments revealed that under worst loading conditions (maximum displacement, with a tube locked in the thermal plate), the specimens failed due to mechanical fatigue in a period corresponding to three to five times the expected service life of a steam generator. Standard internal coil eddy current inspection techniques were not successful in detecting the cracks that had initiated in the Monel tubes in the region of the modeled tubesheet. This made the experimental and analytical fatigue life prediction work even more valuable.
