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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.
J. B. Conway, J. T. Berling, R. H. Stentz
Nuclear Technology | Volume 9 | Number 1 | July 1970 | Pages 31-39
Fuel Cladding Model | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28725
Articles are hosted by Taylor and Francis Online.
Short-term tensile data have been generated using a new experimental technique which allows the true total axial strain rate to be maintained constant all the way to fracture. Tensile data at 650°C (1200°F) for irradiated and unirradiated specimens of AISI 304 and 316 stainless steel are presented and compared. A new relationship between low-cycle fatigue and short-term tensile behavior is discussed and applied to data for irradiated and unirradiated material. The effectiveness of this approach is shown to be excellent. This method should allow the low-cycle fatigue behavior for irradiated material to be estimated with acceptable accuracy. Hold times at peak strain have a noticeable effect on fatigue behavior as evidenced in tests at 650°C. These effects are most pronounced when hold periods are employed in only the tension portion of the cycle. An interesting correlation of hold-time data is presented, based on a logarithmic plot of time to fracture vs the length of the hold period. Another important correlation involves a relationship which identifies a method for estimating hold-time effects from a knowledge of the effect of strain rate on low-cycle fatigue behavior.
