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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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International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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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Fusion Science and Technology
Latest News
Transport by Barge and Road: Shipping Crystal River’s Segmented RPV to Disposal
The Optimized Segmentation process patented by Orano Decommissioning Services was successfully implemented for the first time at the Crystal River Unit 3 (CR-3) decommissioning project in Florida [1]. Using this approach, Orano was able to avoid the time- and resource-intensive process of packaging components into numerous standardized waste containers and significantly reduced the required segmentation activities.
M. Z. Youssef, M. E. Sawan
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 518-523
Technical Paper | Fusion Energy - First Wall, Blanket, and Shield | doi.org/10.13182/FST05-A736
Articles are hosted by Taylor and Francis Online.
The US has considered, among other options, two blanket concepts for Demo reactor in which helium is primarily used to cool the first wall (FW) and structure whereas molten salt (MS) is used as both coolant and breeder. Conventional reduced activation ferritic steel (RAFS, F82H) is used as the structural material in both blanket concepts. The low melting point Flibe (~380°C) is used in the first option while the Flinabe (~305°C) is used in the second option. In this paper, we present the results for assessing the radioactivity and decay heat. This assessment is performed separately for the structural material, the Be multiplier and the breeder (Flibe/Flinabe). The Class C waste disposal rating (WDR) was estimated for each material. For Flibe, Flinabe and Be the WDR is much lower than unity. However, the WDR for F82H is ~0.6-1.3. They are attributed to reactions with Mo and Nb present in F82H with levels of 70 wppm and 4 wppm, respectively. To ensure that F82H qualifies for shallow land burial, it is suggested to reduce these two impurities to ~50 and ~3 wppm, respectively.
