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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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Latest News
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.
Kazumi Iwamoto
Nuclear Science and Engineering | Volume 18 | Number 2 | February 1964 | Pages 189-199
Technical Paper | doi.org/10.13182/NSE64-A18318
Articles are hosted by Taylor and Francis Online.
Irradiated UO2 graphite fuel samples in which most of the fission products had recoiled into the graphite matrix were heated after irradiation, and then leached with nitric acid. The leach-ability of non-gaseous fission products was influenced by fission product concentration, by irradiation temperature, and largely by temperature and period of the heating. A possible rate-controlling mechanism for the fission product loss during the heating is discussed, and the results obtained are compared with some of the earlier work. The data may be interpreted as indicating that the fission products migrate through the graphite crystal to its surface according to a fast and a slow migration step. Escape from the graphite matrix by volatilization is apparently less rapid than the fast migration step; volatilization may be the rate-limiting mechanism in the loss process.
