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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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Empowering the next generation: ANS’s newest book focuses on careers in nuclear energy
A new career guide for the nuclear energy industry is now available: The Nuclear Empowered Workforce by Earnestine Johnson. Drawing on more than 30 years of experience across 16 nuclear facilities, Johnson offers a practical, insightful look into some of the many career paths available in commercial nuclear power. To mark the release, Johnson sat down with Nuclear News for a wide-ranging conversation about her career, her motivation for writing the book, and her advice for the next generation of nuclear professionals.
When Johnson began her career at engineering services company Stone & Webster, she entered a field still reeling from the effects of the Three Mile Island incident in 1979, nearly 15 years earlier. Her hiring cohort was the first group of new engineering graduates the company had brought on since TMI, a reflection of the industry-wide pause in nuclear construction. Her first long-term assignment—at the Millstone site in Waterford, Conn., helping resolve design issues stemming from TMI—marked the beginning of a long and varied career that spanned positions across the country.
E. Duncombe, C. M. Friedrich, W. H. Guilinger
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 194-208
Technical Paper | Fuel | doi.org/10.13182/NT71-A31027
Articles are hosted by Taylor and Francis Online.
The prediction and analysis of fuel rod performance in the CYGRO-3 model is an extended version of the earlier models CYGRO-1 and CYGRO-2 arising from the LWBR development program. The model assumes that circumferential and axial variations in conditions are small compared with radial variations. Fuel and clad are considered as a set of interacting concentric ring elements. Time-dependent values of temperatures, stresses, and deformations (elastic and creep effects) are calculated as the response to a history of coolant water conditions and of rod power and neutron flux. Provision is made to calculate effects of swelling due to pore growth and of thermally induced pore migration in the fuel. An approximation to fuel property changes as a result of cracking are introduced via changes in the elastic relationships. Frictional interaction between fuel and clad when the latter is in the collapsed condition is provided. Forces introduced by fuel rod supports are included. A first-order calculation of straightening moments introduced by circumferential variation in power can also be performed.