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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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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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Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Tsutomu Sakurai, Akira Takahashi, Niro Ishikawa, Yoshihide Komaki
Nuclear Technology | Volume 85 | Number 2 | May 1989 | Pages 206-212
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT89-A34241
Articles are hosted by Taylor and Francis Online.
A method to expel radioiodine from a spent-fuel solution is important for iodine control in reprocessing plants. Many authors have investigated the procedure without considering the influence of other fission products on that procedure. The present work studies the behavior of iodine in a simulated spent-fuel solution containing fission products. When an iodide (1 mg I-) is put into a simulated spent fuel-3.4 M HNO3 solution (100 ml) at 100°C, it is 93.3 to 98.5% volatilized as I2, depending on the carrier gas, the presence of NO2, and the solute concentration. Colloidal iodine constitutes a significant part of the nonvolatile iodine species in this solution, whereas is predominant in a similar solution without fission products. The colloidal iodine varies from 0.4 to 2.9% of the initial iodine, depending on the foregoing experimental conditions. The colloidal iodine consists of such iodides as Pdl2 and Agl, which do not react with NO2 but are decomposed by such iodates as KIO3 and HIO3. Besides acting as carrier , these iodates are able to dissolve the colloid by oxidizing its iodine to I2. A high concentration is required to minimize the colloidal iodine. Increased HNO3 concentration (e.g., 6.1 M) increases the proportion of . The presence of NO2 increases the amount of colloid. Bubbling the solution with a N2 flow retards the formation of the colloid, probably because it prevents the aging of the colloid. Expelling >99% of the iodine from the solution requires additional , besides the action of NO2. These results indicate that the chemical reactions of fission products with iodine can interfere with the volatilization of iodine from the dissolver.
