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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.
A. Hébert
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 261-266
Technical Note | doi.org/10.13182/NSE160-261TN
Articles are hosted by Taylor and Francis Online.
The double-heterogeneity treatment is available in many lattice codes to represent the effect of one or many stochastic media on the deterministic solution of the neutron transport equation. A stochastic medium is a mixture of a diluent matrix with cylindrical or spherical microstructures of different sizes. Different models have been presented in the past, some limited to the collision probability method and others limited to the method of characteristics. We have reformulated these existing models in a uniform framework and introduced a scattering reduction, making them compatible with any solution technique of the neutron transport equation. This new approach has been implemented in the Dragon Version4 lattice code in a generic way that is interoperable with the overall code features. This approach can easily be implemented within any existing code dedicated to the solution of the transport equation.
