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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
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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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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.
Masaki Kitagawa, Hiroshi Hattori, Akira Ohtomo, Tetsuo Teramae, Junichi Hamanaka, Hiroshi Ukikusa
Nuclear Technology | Volume 66 | Number 3 | September 1984 | Pages 675-684
H. Design Codes and Life Prediction | Status of Metallic Materials Development for Application in Advanced High-Temperature Gas-Cooled Reactor / Material | doi.org/10.13182/NT84-A33489
Articles are hosted by Taylor and Francis Online.
A design guide for high-temperature gas-cooled reactor components is proposed and applied to the design and construction of the l.5-MW(thermal) helium heat exchanger test loop for nuclear steelmaking. To assure that the design method covers all conceivable failure modes and has a large enough safety margin, a series of lifetime tests of partial model may be needed. For this project, three types of model tests are performed. A lifetime test of an in-scale model of the center manifold pipe and eight heat exchanger tubes is described. Applied load is the combination of the simulated thermal expansion stress (deformation controlled quantity) and primary stress by internal pressure of tubes. The level of both loads is much higher than the corresponding values in the actual plant, which causes failure of the model in a shorter time. The eight tubes are arranged so that each is subjected to different damage conditions. The lifetime tests ran for 48 days, and six tubes out of eight failed during the test at the highest stressed stub tubes. Other parts of the components were found to be sound after the test. A damage criterion with a set of material constants and a simplified method for stress-strain analysis for a stub tube under a three-dimensional load are newly developed and used to predict the lives of each tube. The predicted lives are compared with the experimental lives and good agreement is found. The lifetime test model is evaluated according to the proposed design guide, and it is found that the guide has a safety factor of ∼200 in life for this particular model.