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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.
R. N. Nair, Y. S. Mayya, V. D. Puranik
Nuclear Technology | Volume 153 | Number 1 | January 2006 | Pages 53-69
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3689
Articles are hosted by Taylor and Francis Online.
A generic method has been developed to evaluate the reasonable upper-bound (RUB) dose from near-surface radioactive waste disposal facilities through a drinking water pathway. This generic method has been developed by applying a safety assessment model to seven near-surface radioactive waste disposal sites in India. The concentrations and effective radiation dose rates due to different radionuclides are evaluated at different distances from the disposal facilities. The peak dose rates received by members of the public at these distances are given per unit nuclear power capacity at the site [mSv/yr per GW(electric)yr]. The product of these normalized peak dose rates and the total existing or projected nuclear power capacity at a site [GW(electric)yr] will indicate the RUB dose rates from the near-surface disposal facility through a drinking water pathway at different distances. Results indicate that the sites can be grouped into two categories: (a) sites having groundwater velocity >10 cm/day (category 1) and (b) sites having groundwater velocity <10 cm/day (category 2). The variation in the dose rates between each category of sites is found to be small. Based on this finding, a generic method has been developed to evaluate the RUB dose rates to members of the public from the near-surface radioactive waste disposal facilities as a function of distances and nuclear power capacity. It is observed that the RUB dose rates at 1, 2, and 3 km are ~0.03, 0.02, and 0.01 mSv/yr, respectively, for category 1 sites for a nuclear power capacity of 1 GW(electric). These dose rates are reduced by a factor of 2 for category 2 sites. This generic method is found useful for the screening analysis of proposed low-level radioactive waste disposal sites as it estimates the RUB effective dose rates as a function of distance and nuclear power capacity for different categories of sites.