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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.
Yi-Chun Lin, Shi-Hwa Su, Hui-Yu Tsai, Shiang-Huei Jiang
Nuclear Technology | Volume 168 | Number 1 | October 2009 | Pages 74-78
Detectors | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (Part 1) / Radiation Measurements and Instrumentation | doi.org/10.13182/NT09-A9103
Articles are hosted by Taylor and Francis Online.
The purpose of this research is to estimate the wall effect of spherical graphite-walled cavity chambers using the Monte Carlo method to establish a 60Co air-kerma standard at the National Radiation Standard Laboratory of the Institute of Nuclear Energy Research (NRSL/INER), Taiwan. For more than a decade, the validity of the wall correction term kwall determined by linear-extrapolation methods has been strongly challenged by the Monte Carlo method. In this paper, one goal was to evaluate in detail kwall for spherical chambers varying with wall thickness (0.1 to 2.5 cm), cavity size (1 to 1000 cm3), and incident photon energy (0.02 to 1.33 MeV). The other goal was to obtain kwall for self-fabricated, spherical chambers and then compare it with the historical values in 2003. A significant increase of 0.3% for air kerma in the 60Co field was expected. The difference of bilateral comparison between NRSL/INER and the Australian Radiation Protection and Nuclear Safety Agency was reduced when the calculated kwall, instead of the original estimated value of kwall, was applied for the derivation of the calibration factor. The NRSL/INER primary standards for air kerma will be adjusted in the near future to reflect the changes in kwall described in this work.
