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Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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.