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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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
Four million nuclear jobs by 2050: Who will do them?
Industry leaders from around the globe met this month to discuss the talent development that will be necessary for the long-term success of the nuclear industry.
The International Conference on Nuclear Knowledge Management and Human Resources Development, hosted by the International Atomic Energy Agency, was held in Vienna earlier this month. Discussed there was the agency’s forecast for nuclear capacity to more than double—or hopefully triple—by 2050 and the requirement of more than four million professionals to support the industry.
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.
