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.
Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Apr 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
June 2024
Nuclear Technology
May 2024
Fusion Science and Technology
Latest News
NRC wants input on Hermes 2 test reactor construction permit
The Nuclear Regulatory Commission is seeking input on its draft environmental assessment and draft finding of no significant impact for Kairos Power’s application to build the Hermes 2 test reactor facility in Oak Ridge, Tenn.
M. F. Smith, R. D. Watson, J. B. Whitley, J. M. McDonald
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 1174-1183
Beryllium Technology | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A39927
Articles are hosted by Taylor and Francis Online.
Materials testing of S-65-B grade beryllium has been conducted in order to evaluate the use of this material for limiter surfaces in the ISX-B and JET tokamaks. Selected thermal and mechanical properties were measured at temperatures up to 700 °C. These measurements revealed that S-65-B has exceptionally high ductility (up to roughly 50% elongation) at temperatures expected in normal operation of a beryllium limiter. Thermal fatigue tests under conditions relevant to limiters in ISX-B and JET were also performed using the Sandia National Laboratories Electron Beam Test System (EBTS). Results from these tests were compared to calculated results based on elastic-plastic finite element stress analyses. It was concluded from these tests and analyses that properly designed beryllium limiters should survive normal operation in ISX-B, JET, and similar devices without serious structural failure. Some degree of surface cracking can be expected, however, unless cyclic plastic deformation at the heated surfaces can be adequately controlled by careful design of the limiter.