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Division Spotlight
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.
Meeting Spotlight
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
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Giuseppe Modolo, Reinhard Odoj
Nuclear Technology | Volume 117 | Number 1 | January 1997 | Pages 80-86
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT97-A35337
Articles are hosted by Taylor and Francis Online.
According to the current state of the art in reprocessing technology, the 129I contained in spent fuel elements can be completely transferred to the dissolver off-gas and efficiently adsorbed on AgNO3-impregnated silica (AC 6120). For future transmutation, the 129I should again be separated selectively and as completely as possible (>99%) from the AC 6120 adsorption matrix. Experimental studies show that a quantitative recovery of the iodine is possible by wet chemical and thermal processes. Extraction experiments using iodine-loaded AC 6120 with sodium sulfide solution provide recovery rates of 99 ± 1%. Reduction with hydrogen at 500°C, in which gaseous HI was liberated, provided recovery rates of >99%. After the separation of iodine, the reduced AC 6120 can be used again as an adsorbent for molecular iodine.
