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Division Spotlight
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.
Meeting Spotlight
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
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
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.
M. Kelm, E. Bohnert
Nuclear Technology | Volume 129 | Number 1 | January 2000 | Pages 123-130
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT00-A3051
Articles are hosted by Taylor and Francis Online.
The radiation chemical reactions in gamma-irradiated 2 to 5.3 mol/l NaCl solutions were mathematically modeled by elementary reactions proceeding in parallel. The calculations showed that if all radiolytic gases could escape from the solution, only three final compounds would be formed proportional to the dose and independent from the dose rate: H2, O2, and chlorate. All other products and intermediates reached a steady-state concentration after ~1 kGy. Within certain limits, the yields of final radiolytic products were determined solely by the primary G values of H2 and H2O2. The results of the corresponding irradiation experiments carried out in glass ampoules up to ~1 MGy were in good agreement with the calculations. The simulation of the radiolysis under the condition that all gaseous products remain dissolved in the solution showed a nearly constant formation rate for hydrogen and oxygen. As opposed to this, the experiments conducted in autoclaves resulted in nearly steady-state conditions for the gases at some 100 kGy at a pressure of ~35 bars. For chlorate, the experiments and the calculation gave a constant concentration of a few micromoles per litre in 5.3 mol/l NaCl solution. A better correspondence between experiments and the simulation was achieved for the gases when the reaction model was extended for interaction of corrosion products from the autoclaves.