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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.
Milan Marek
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 943-948
Miscellaneous | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Radioactive Waste Management and Disposal | doi.org/10.13182/NT09-A9331
Articles are hosted by Taylor and Francis Online.
To support the transport of spent nuclear fuel from Czech research reactors of Russian origin back to the Russian Federation, a special VPVR/M transport cask was designed at SKODA JS, Czech Republic. In 2007, the shipment of 16 VPVR/M casks with EK-10 fuel of 10 wt% 235U, IRT-2M fuel of 80 wt% 235U, and IRT-2M fuel of 36 wt% 235U expended at the LVR-15 research facility since 1957 was realized. The VPVR/M cask was designed for all fuel types used in Russian research reactors of similar designs, which were built in many countries outside of Russia.A revised version of the ORIGEN 2.2 code was used for depletion calculations of 35 types of irradiated fuel. Shielding analyses of the VPVR/M cask were performed using the DORT code with the revised BUGLE-96 multigroup cross-section library based on ENDF/B-VI Release 3. The criticality of the cask loaded with the highest-reactivity fuel was evaluated with the MCNP code using the DLC-200 cross-section data library using the fresh fuel approach.The isotopic inventory of IRT-3M fuel of 36 wt% 235U burned up to 184 MWd/kg U was identified as the bounding value. The sources of gamma rays for shielding calculations, neutron sources for shielding and criticality calculations, and heat sources were consequently evaluated. The original design of the cask was optimized with respect to the minimum weight needed for the conservation of the required shielding properties. In compliance with the regulatory requirements for spent-fuel storage and transport casks, the subcriticality of the system met the criticality safety criterion of keff < 0.95 for all the fuel types evaluated. The cask fulfilled Czech safety criteria as well as International Atomic Energy Agency regulations for subcriticality, shielding, heat cooling, and structure requirements.
