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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
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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.
Koji Oishi, Yujiro Ikeda, Chikara Konno, Tomoo Nakamura
Fusion Science and Technology | Volume 18 | Number 2 | September 1990 | Pages 291-309
Technical Paper | Shielding | doi.org/10.13182/FST90-A29301
Articles are hosted by Taylor and Francis Online.
The principal components of concrete were irradiated by 14-MeV neutrons for measurement of their induced activities to verify the activation calculation code THIDA-2 and its related cross-section library CROSSLIB. The observed radioactive nuclides, whose half-lives range from minutes to years, were 28Al, 29Al, 27Mg, 44K, 41Ar, 56Mn, 42K, 24Na, 43K, 48Sc, 47Sc, 47Ca, 46Sc, 54Mn, and 22Na, Experimental and calculated results were compared. Good agreement was obtained within ±20%, for 28Al, 56Mn, 42K, 24Na, 48Sc, 47Ca, 46Sc, and 54Mn with well-estimated production cross sections. Large differences were also observed, however, ranging in value from −50 to +100%, for the other nuclides. The cross-section values near 14 MeV for these nuclides were replaced with the cross-section data measured at the Fusion Neutronics Source at the Japan Atomic Energy Research Institute. Recalculation was performed using the newly estimated group cross sections derived from these data, and agreement between experiment and calculation was improved to within ±20%. From this experimental study, it was proved that the uncertainties of the activation cross-section values could satisfactorily explain the discrepancies of the induced activity calculation.
