ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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!
Latest Magazine Issues
Jul 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
August 2025
Nuclear Technology
Fusion Science and Technology
July 2025
Latest News
Hash Hashemian: Visionary leadership
As Dr. Hashem M. “Hash” Hashemian prepares to step into his term as President of the American Nuclear Society, he is clear that he wants to make the most of this unique moment.
A groundswell in public approval of nuclear is finding a home in growing governmental support that is backed by a tailwind of technological innovation. “Now is a good time to be in nuclear,” Hashemian said, as he explained the criticality of this moment and what he hoped to accomplish as president.
K. Petersen, H. Barthels, H. E. Drescher, C. B. Von Der Decken, N. Iniotakis, W. Schenk, R. Schulten
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 306-311
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32331
Articles are hosted by Taylor and Francis Online.
Unrestricted core heatup analysis based on recent experimental investigations of heat, gas, and fission product transport mechanism under ultimate accident conditions proves for the example of the 500-MW(thermal) plant the inherent safety potential of the pebble-bed high-temperature reactor. Under the hypothetical assumptions of depressurization of the primary circuit through a large hole within the prestressed concrete reactor vessel top region and the failure of all heat sinks, including the liner cooling system, the core structure, fuel elements, and consequently the essential fission product barriers remain undamaged. The integrated 137Cs contamination of the containment after depressurization rises only to 1 Ci after 100 h.