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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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Nuclear Science and Engineering
November 2025
Nuclear Technology
Fusion Science and Technology
October 2025
Latest News
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.
M. A. Abdou, R. E. Nygren, E. Opperman, R. Puigh, G. Wire, G. D. Morgan, C. A. Trachsel, R. Gold
Fusion Science and Technology | Volume 4 | Number 2 | September 1983 | Pages 1043-1051
Next-Generation Devices | doi.org/10.13182/FST83-A22996
Articles are hosted by Taylor and Francis Online.
The FED/INTOR Critical Issues activity examined three key testing requirements that have the largest impact on the design, operation and cost of FED/INTOR. These are: 1) the total testing time (fluence) during the device lifetime, 2) the minimum number of back-to-back cycles, and 3) the neutron wall load. These requirements were quantified by investigating the benefits/risks to the DEMO from testing structural materials, blankets, and main reactor components in FED/INTOR.
