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.
H.U. Borgstedt, M. Grundmann, J. Konys
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 536-540
Material Engineering — Behavior | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40094
Articles are hosted by Taylor and Francis Online.
Liquid lithium, which is under consideration as blanket fluid of fusion reactors, is more corrosive against austenitic and martensitic-ferritic steels than liquid sodium. The results of corrosion studies in flowing lithium as well as of tests on the mechanical behaviour of the materials in stagnant lithium at 550°C are presented and discussed. The candidate materials are nearly insensitive against liquid metal embrittlement in lithium at 200 to 250°C. After precorrosion in lithium at 550°C, they show more or less brittle fracture behavior in lithium of 200 to 250°C.