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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
Meeting Spotlight
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
Standards Program
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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Nuclear Science and Engineering
October 2021
Nuclear Technology
Fusion Science and Technology
August 2021
Latest News
Helping to save the plant safety puzzle: An overview of PRA
Probabilistic risk assessments (PRAs) have advanced the safe operation of the U.S. reactor fleet over many decades. Risk insights from PRAs have provided information from many different perspectives, from what is most important to maintain at a facility to a better understanding of how to address new information regarding safety issues. The methods and tools that have supported the creation and enhancement of PRA models were established through multiple decades of research, starting with WASH-1400, The Reactor Safety Study,1 published in 1975, through the comprehensive plant-specific models in use today.
V. A. Nikolaev, I. Gorynin, N. N. Alekseenko, Am. Amaev
Item ID: 690051|ISBN: 978-0-89448-564-0
1997|1st Edition|282 pages
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Description
This book describes the current state of knowledge about pressure vessel material selection, fabrication (including welding), the changes in properties in service, and response to high-temperature annealing. In contrast to the bad reports of inadequate attention to reactor safety in the former Soviet Union, this book shows that the question of pressure vessel performance has received proper attention, and a strong scientific base underlies the assessment of vessel life. This book should be read by reactor designers and operators and their scientific colleagues throughout the world.
