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Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
2022 ANS Winter Meeting and Technology Expo
November 13–17, 2022
Phoenix, AZ|Arizona Grand Resort
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
Fusion Science and Technology
Maintaining RIPB in commercial LWRs
The new standard ANSI/ANS-30.3-2022, Light Water Reactor Risk-Informed, Performance-Based Design, has just been issued by the American Nuclear Society. Approved by the American National Standards Institute (ANSI) on July 21, 2022, the standard provides requirements for the incorporation of risk-informed, performance-based (RIPB) principles and methods into the nuclear safety design of commercial light water reactors. The process described in this standard establishes a minimum set of process requirements the designer must follow in order to meet the intent of this standard and appropriately combine deterministic, probabilistic, and performance-based methods during design development.
Sergey Smolentsev, Siegfried Malang
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 201-205
Tritium, Safety, and Environment | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | dx.doi.org/10.13182/FST09-A8902
Articles are hosted by Taylor and Francis Online.
A new modification of the flow channel insert (FCI) called "double-layer" or "nested" FCI (nFCI) is assessed numerically for the poloidal duct flows in the dual-coolant lead-lithium (DCLL) blanket under the US DEMO outboard (OB) blanket conditions. The proposed nFCI mitigates the thermal stress while providing sufficient thermal insulation and reducing the MHD pressure drop.