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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.
Sanjeev Kumar Sharma, Manoj Kansal, N. Mohan, P. K. Malhotra, S. G. Ghadge
Nuclear Science and Engineering | Volume 169 | Number 2 | October 2011 | Pages 222-227
Technical Paper | doi.org/10.13182/NSE09-16
Articles are hosted by Taylor and Francis Online.
One of the important issues in severe reactor accident scenarios is the containment integrity and the characteristics of the source term that governs the ultimate radioactive releases to the environment. The releases are in the form of aerosols that are generated by the condensation of volatile fission products released from fuel, within the containment, during the severe accident. A loss-of-coolant accident with simultaneous failure of the emergency core cooling system has been postulated for a study of such aerosols. For the aerosol behavior in the containment, various removal mechanisms, such as gravitational settling, diffusional plate-out, and diffusiophoresis, and growth processes such as agglomerations and condensation have been included. The transport process such as leakage from the containment has also been modeled. This paper discusses the results of the studies carried out to estimate aerosols' behavior in the Tarapor Atomic Power Station (TAPS)-3&4 containment following their release during the postulated accident condition. It was found that the gravitational settling is the major aerosol removal mechanism following the postulated severe accident.
