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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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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Tsutomu Sakurai, Akira Takahashi, Niroh Ishikawa, Yoshihide Komaki, Mamoru Ohnuki
Nuclear Technology | Volume 116 | Number 3 | December 1996 | Pages 319-326
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT96-A35287
Articles are hosted by Taylor and Francis Online.
The quantity of iodine in spent-fuel solutions tends to decrease with an increase in the dissolution rate. This phenomenon is ascribed to the presence of nitrous acid (HNO2) generated in the dissolution process because of the following three findings: (a) in a hot nitric acid solution, the steady-state HNO2 concentration increases with an increase in the rate of its production and decreases with an increase in temperature, (b) the HNO2 decreases the quantity of colloidal iodine (the main component of residual iodine in a simulated spent-fuel solution) in proportion to its concentration up to ∼3.0 × 10−3 M, and (c) a higher dissolution rate of UO2 causes a higher HNO2 production rate, hence, a higher HNO2 concentration in the solution. The HNO2 did not appear (i.e., [HNO2] <2 × 10−4 M) in the dissolution of a UO2 pellet (∼1 g) with a low dissolution rate, 0.4 g/h of UO2 at 100°C. When high concentrations of I2 and NO2 (263 parts per million of I2 and 38% of NO2) in an N2flow were passed through a simulated spent-fuel solution at 100°C, the predicted colloid of AgI was produced as a chemical equilibrium product of the reaction AgI(s) + 2HNO3(aq) = I2(aq) + AgNO3(aq) + NO2(g) + H2O(l). This finding suggests that colloidal iodine may be produced secondarily in the dissolver of reprocessing plants; this can be one of the reasons why the residual iodine quantity in spentfuel solutions is higher in reprocessing plants than in laboratory-scale experiments.