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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
ARPA-E announces $40 million to develop transmutation technologies for UNF
The Department of Energy’s Advanced Research Projects Agency–Energy (ARPA-E) announced $40 million in funding to develop cutting-edge technologies to enable the transmutation of used nuclear fuel into less-radioactive substances. According to ARPA-E, the new initiative addresses one of the agency’s core goals as outlined by Congress: to provide transformative solutions to improve the management, cleanup, and disposal of radioactive waste and spent nuclear fuel.
Thi Thanh Thuy Nguyen, Kwang Soon Ha, Jin Ho Song, Sung Il Kim
Nuclear Science and Engineering | Volume 193 | Number 8 | August 2019 | Pages 916-925
Technical Paper | doi.org/10.1080/00295639.2019.1574118
Articles are hosted by Taylor and Francis Online.
A new empirical model is proposed for estimating the amount of volatile iodine in an aqueous phase. The volatile iodine concentration is estimated for highly irradiated CsI solutions in which the pH of the solution changes. The reaction of CsI solution with water radiolysis products is not balanced because radiolysis products are continuously produced under irradiation. Thus the kinetic of the chemical equation is important to determine iodine behavior in a CsI solution. An empirical model for the kinetic equation including the oxidation and reduction reaction is proposed. The proposed model was validated with a wide range of experimental data. A comparison of the experiments and predictions by the model indicated that the predicted volatile iodine from CsI solution with a concentration of 10−3 to 10−4 M was in good agreement. For 10−5 M CsI solution, the predicted iodine concentration was much smaller than experimental data due to the fact that I− was rapidly converted to IO3−.