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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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.
Min Woo Seo, Jae Woo Park
Nuclear Technology | Volume 168 | Number 3 | December 2009 | Pages 938-942
Miscellaneous | Special Issue on the 11th International Conference on Radiation Shielding and the 15th Topical Meeting of the Radiation Protection and Shielding Division (PART 3) / Radiation Protection | doi.org/10.13182/NT09-A9330
Articles are hosted by Taylor and Francis Online.
A fiber-optic dosimeter model is constructed with a small piece of Gd2SiO5 (GSO) scintillator optically attached to a low attenuating plastic optical fiber. The lights generated in the scintillator are transmitted through the fiber and read by a current-type photomultiplier tube (PMT). The dosimeter model was tested with two 60Co standard sources of 1.85 and 37 MBq by measuring the PMT current as a function of the source-to-detector distance. It was then tested in a 60Co irradiation chamber with an activity of [approximately]244.2 TBq. MCNPX simulations were performed for the source and dosimeter arrangements to calculate the deposited energy in the GSO scintillator. When tested with standard 60Co sources of 1.85 and 37 MBq, the dosimeter model did not produce satisfactory results. However, better results were obtained with the higher-activity source. In the test in a 60Co irradiation chamber of 244.2 TBq, the measured data well coincide with the MCNPX simulation results. In a direct comparison with a Farmer-type ion chamber, it is found the dosimeter readings can be simply converted to the air kerma doses by proper calibration.
