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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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!
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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
N. Scott Cannon, Gary L. Wire
Nuclear Technology | Volume 63 | Number 1 | October 1983 | Pages 50-62
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT83-A33302
Articles are hosted by Taylor and Francis Online.
A new simulated transient test capability is introduced that allows controlled biaxial strain-rate (CBSR) tests on fast reactor cladding to be performed at constant test temperatures ranging from 425 to 650°C and constant diametral strain rates between 10−5 and 10−3/s. The CBSR test results from both irradiated and unirradiated 20% cold-worked Type 316 stainless steel are reported. A mathematical expression describing CBSR strengths was developed from tensile data. The CBSR ductility was generally found to be reduced from corresponding tensile results by roughly an order of magnitude. For unirradiated cladding, diametral failure strain was relatively strain-rate independent below 650°C, and at 650°C, failure strains increased with decreasing strain rate. Following fast reactor irradiation at 370 to 680°C cladding, diametral failure strains increased with increasing irradiation temperature. The sensitive diameter measurement apparatus allowed strain determinations showing the importance of anelastic effects at low plastic strains.