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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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Latest News
Deep Isolation validates its disposal canister for TRISO spent fuel
Nuclear waste disposal technology company Deep Isolation announced it has successfully completed Project PUCK, a government-funded initiative to demonstrate the feasibility and potential commercial readiness of its Universal Canister System (UCS) to manage TRISO spent nuclear fuel.
C. E. Kessel, T. Bohm, M. S. Tillack, P. Titus, Y. Zhai
Fusion Science and Technology | Volume 77 | Number 7 | November 2021 | Pages 519-531
Technical Paper | doi.org/10.1080/15361055.2021.1909988
Articles are hosted by Taylor and Francis Online.
Restraining the size of fusion power plants is considered an important avenue to make them a competitive energy source among other forms of energy production. The most critical contributor to the size of a tokamak is the inboard radial build, composed of multiple components with various functions. This build is the ultimate limit to size reduction. The Fusion Nuclear Science Facility is reviewed and each element of the inboard build is described, showing that the build, including breeding blanket, structural ring, vacuum vessel, low-temperature shield, and toroidal field and central solenoid (CS) coils, contributes 2.9 m of build, with 0.6 m of bore hole inside the CS coil, or 3.5 m to reach the plasma scrape-off layer. This implies that it would be challenging to make a significantly smaller build and simultaneously meet all the engineering requirements.