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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Dry Ice Blasting: A Game-Changer for Safe Cleaning and Decontamination in Nuclear Power Plants
The nuclear energy industry is critical not only for meeting the world’s growing demand for electricity but also for advancing global decarbonization goals. As the sector evolves—through life extensions of existing plants, decommissioning, innovations like small modular reactors (SMRs) and microreactors, and new facility construction—the need for safe, efficient, and environmentally responsible maintenance and decommissioning continues to grow. Whether a plant is coming online, operating beyond its original design life, or entering decommissioning, cleanliness and operational integrity remain non-negotiable. That’s where dry ice blasting stands out—a powerful, safe cleaning method ideally suited for the high-stakes demands of nuclear environments.
Koichi Maki, Chikara Konno, Fujio Maekawa, Hiroshi Maekawa, Katsumi Hayashi, Kobun Yamada
Fusion Science and Technology | Volume 36 | Number 1 | July 1999 | Pages 52-61
Technical Paper | doi.org/10.13182/FST99-A91
Articles are hosted by Taylor and Francis Online.
In traditional shielding design, thicknesses of shieldings have been determined so that calculated shielding properties multiplied by safety factors do not exceed design limits. A shielding design margin is defined for the safety factors that are included in the estimated shielding thicknesses in the design process. Sensitivities of the shielding design margin to the fusion reactor scale and amount of material are examined for a typical fusion experimental reactor such as the International Thermonuclear Experimental Reactor (ITER). From these investigations, supposing the shielding design margin can be made smaller by up to half the typical value of 3 used in a reactor, the amount of toroidal coil, transformer coil, and other torus component materials can be reduced by 1.5, 0.7, and 0.7%, respectively. If one includes a reactor building and accessory facilities that are not affected by the shielding design margin, the whole reactor material reduction becomes 0.55%. Since reactor cost is assumed to be proportional to the amount of material, the 0.55% reduction may be worth $55 million when the estimated price of the reactor is assumed to be $10 billion.