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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
April 2025
Latest News
State legislation: Delaware delving into nuclear energy possibilities
A bill that would create a nuclear energy task force in Delaware has passed the state Senate and is now being considered in the House of Representatives.
Ryo Suzuki, Masakatsu Saito, Toshihisa Hatano
Fusion Science and Technology | Volume 44 | Number 1 | July 2003 | Pages 242-246
Technical Paper | Fusion Energy - Divertor and Plasma-Facing Components | doi.org/10.13182/FST03-A341
Articles are hosted by Taylor and Francis Online.
The fracture strength was estimated for copper-alloy CuCrZr, and their HIPed joints with SS316L and CuCrZr, which were the candidate materials consisting of the First Wall of ITER. Fracture toughness and fatigue crack propagation ratio of those materials were superior to those of copper-alloy DS-Cu and its HIPed joint with SS316. It was confirmed that the cracks near the CuCrZr/SS316L HIPed boundary was propagated in copper-alloy along the interface at a distance of about 10m from the interface. The lost of ductility of all materials caused the decrement of fracture toughness and increment of crack propagation ratio in high temperature (573K).