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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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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Latest News
Modernizing I&C for operations and maintenance, one phase at a time
The two reactors at Dominion Energy’s Surry plant are among the oldest in the U.S. nuclear fleet. Yet when the plant celebrated its 50th anniversary in 2023, staff could raise a toast to the future. Surry was one of the first plants to file a subsequent license renewal (SLR) application, and in May 2021, it became official: the plant was licensed to operate for a full 80 years, extending its reactors’ lifespans into 2052 and 2053.
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).
