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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
Yoshiyuki Asaoka, Kunihiko Okano, Tomoaki Yoshida, Ryouji Hiwatari, Seiji Mori
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 1018-1022
Safety and Environment | doi.org/10.13182/FST01-A11963376
Articles are hosted by Taylor and Francis Online.
Radioactive waste generated from the CREST reactor has been evaluated. Activation of blankets and shields used during a plant lifetime was evaluated by an activation calculation code taking into accounts of the distribution of neutron wall loading and the scenario of blanket replacement. Limits on surface dose limits define the feasibility of recycling by remote handling (RHR) and by hands-on operation (HOR). After 50 years for decay of activated components, surface dose rate of most of components exceeds 10 mSv/h and cannot be recycled. Some of shields are lower than 10 mSv/h and have a possibility of RHR. After 100 years, surface dose rate of all components is lower than 3 mSv/h, and RHR is feasible. Half of shields are lower than 0.01 mSv/h and have a possibility of HOR. After 125 years, dose rate of all components is lower than 1 mSv/h. RHR with a relatively simple shielding precaution may be feasible. In the cases of 150 years or later, little degradation of dose rate can be expected. Therefore, the used components should be managed within approximately 125 years by suitable methods.