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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.
Stephen M. Bajorek, Michael Y. Young
Nuclear Technology | Volume 132 | Number 3 | December 2000 | Pages 375-388
Technical Paper | Thermal Hydraulics | doi.org/10.13182/NT00-A3151
Articles are hosted by Taylor and Francis Online.
During the blowdown phase of a large-break loss-of-coolant accident (LOCA), high-powered regions of a nuclear reactor core exceed the critical heat flux, and peak-cladding temperatures (PCTs) in the range from 1033 to 1255°C (1400 to 1800°F) can occur before high flow rates terminate the temperature rise. Following the blowdown PCT, the core is cooled by a dispersed droplet flow at moderately high pressures. Heat transfer during this blowdown cooling period removes a significant portion of stored energy from the core and can lead to quench. Energy removal during this period is an important feature in the AP600 advanced passive plant design because the design includes good communication between the core and water in the reactor vessel upper head.For realistic LOCA calculations performed according to the revised 10 CFR 50.46 regulation using the code scaling, applicability, and uncertainty methodology, it becomes necessary to quantify those physical processes that have a dominant effect on the transient. Blowdown cooling heat transfer determines the initial condition of the core at the start of reflood and thus is a major contributor to the propagation of uncertainty in later periods of the transient.The approved Westinghouse best-estimate LOCA methodology uses the WCOBRA/TRAC-MOD7A code to predict the large-break LOCA transient. Quantification of blowdown cooling heat transfer coefficients (HTCs) was performed by development of a driver-plotter routine based on the WCOBRA/TRAC heat transfer package. Known fluid conditions corresponding to experimental data were then used to generate predictions of blowdown cooling HTCs. A distribution, developed from comparisons to several experimental tests, of predicted versus measured HTCs shows the average bias and uncertainty in the heat transfer package.Based on driver-plotter routine calculations of blowdown HTCs measured in the Oak Ridge National Laboratory blowdown tests and Idaho National Engineering Laboratory high-pressure single-tube tests, a new correlation for direct-contact heat transfer is proposed. Use of the new model was found to provide significantly improved agreement between predicted and measured HTCs.