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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
P. E. Reagan, F. L. Carlsen, R. M. Carroll
Nuclear Science and Engineering | Volume 18 | Number 3 | March 1964 | Pages 301-318
Technical Paper | doi.org/10.13182/NSE64-A20051
Articles are hosted by Taylor and Francis Online.
Fission-gas release from pyrolytic-carbon-coated uranium carbide particles was studied as part of a fuel-development program for gas-cooled reactors. The particles were contained in a test capsule between concentric cylinders of porous graphite and were heated by fission heat. A small flow of helium was used to sweep the fission gas from the test capsule. Uranium carbide particles coated with three types of pyrolytic carbon (laminar, columnar, and duplex), as well as uncoated uranium carbide particles, were irradiated at temperatures up to 1800 F. The steady-state fission-gas release rates were measured as a function of temperature and burnup. All three coating types greatly reduced the fission-gas release rate from uranium carbide particles; the duplex coating was much better than the laminar or the columnar coatings. Post-irradiation examination revealed less than 0.1% broken coatings for the duplex coating. A radiation-induced reaction zone was observed at the fuel/coating interface for all three types. A correlation was made between the number of broken coatings and fission-gas release rate.
