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Conference Spotlight
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.
Sherly Ray, S. B. Degweker, Rashmi Rai, K. P. Singh
Nuclear Science and Engineering | Volume 184 | Number 4 | December 2016 | Pages 473-494
Technical Paper | doi.org/10.13182/NSE15-127
Articles are hosted by Taylor and Francis Online.
The BOXER3 code was developed in the Bhabha Atomic Research Centre during the 1980s as a three-dimensional code for the analysis of a pressurized heavy water reactor supercell containing fuel, moderator, and a reactivity device inserted perpendicular to the fuel channel, with options for carrying out calculations in a general two-dimensional geometry (infinite and homogeneous in one direction) and a one-dimensional plane geometry. Taking into account the computing resources available then, the code was run in few groups after obtaining condensed group cross sections for various materials from a one-dimensional multigroup calculation.
In this paper, we describe various developments carried out recently for enabling its use as an assembly-level lattice-burnup code. In addition to the collision probability method originally available, the method of characteristics for solving the multigroup transport equation has been added. This development permits the treatment of anisotropic scattering wherever necessary and available in cross-section libraries. Other developments include coupling of the code to the WIMS 69/172-group library, a method for the evaluation of the pin-dependent Dancoff factor, and the introduction of burnup. The transport equation in the collision probability method is cast in a form more suitable for iterations as well as for the method of renormalization of collision probabilities used in the work. The analysis of several benchmark problems has been carried out and the results obtained using the new code are presented.