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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
V. A. Kazakov, A. S. Pokrovsky, A. V. Smirnov
Nuclear Technology | Volume 53 | Number 3 | June 1981 | Pages 392-406
Technical Paper | Nuclear Fuel Cycle Education Module / Material | doi.org/10.13182/NT81-A32648
Articles are hosted by Taylor and Francis Online.
The effect of neutron irradiation on the mechanical properties, structure, and peculiarities of void formation in the Mo-Zr-B alloy within the temperature range from 400 to 1080° C and fluences (1.3 to 11.5) · 1025 n/m2 (>0.1 MeV) has been investigated. The results from radiation studies of poly- and monocrystalline molybdenum, Mo—0.12 Zr—0.16 Ti alloy and of the Mo-Zr-B alloys with different initial thermal treatment have been analyzed. At temperatures of 950 and 1080°C, the voids of nonequiaxial shape are formed, and at 1010°C only planar defects, supposedly thin precipitates, are observed. These results show a minimum swelling of the Mo-Zr-B alloy at 1010°C. It is expected that the peculiarities of void evolution in the Mo-Zr-B alloy are due to the impurity precipitation on void faces. A good correlation of the calculated and experimental values for radiation strengthening of the alloy as a result of voids and dislocation loops within a wide range of their sizes and concentrations was observed. A connection was found between the reduction of the uniform elongation within the temperature range from 400 to 900° C and voidage parameters. A maximum strengthening of the alloy takes place after irradiation at 635°C, which results from a high density of both 1.5-nm-diam voids and the dislocation loops.
