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Division Spotlight
Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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.
J. Mazeika, R. Petrosius, V. Jakimaviciute-Maseliene, D. Baltrunas, K. Mazeika, V. Remeikis, T. Sullivan
Nuclear Technology | Volume 161 | Number 2 | February 2008 | Pages 156-168
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT08-A3920
Articles are hosted by Taylor and Francis Online.
The paper presents the long-term safety assessment of the Maisiagala radioactive waste repository (Lithuania) using the advanced computer codes DUST, FEFLOW, and AMBER. The software DUST was employed for calculations of the one-dimensional leaching flux of radionuclides from the repository vault and subsequent transport in the unsaturated zone. Using the mass flux of radionuclides calculated in DUST as a source to the aquifer, the software FEFLOW was used for two-dimensional assessment of activity concentrations of radionuclides in groundwater. Using the groundwater concentrations calculated in FEFLOW, the code AMBER was used to calculate the dose over time at four hypothetical wells downstream from the repository. The well distances ranged from 150 to 1600 m.When the hypothetical drinking water well is installed 150 m from the repository (close to the outside perimeter of the controlled area), the highest effective doses will arise from 3H, 36Cl, and 239Pu. The doses determined by 3H and 36Cl may exceed a dose limit of 1 mSv/yr for 50 to 230 yr after the closure of the facility (1989). The dose of 239Pu will remain almost constant for >60 000 yr after the closure, yet it will not exceed the dose limit value. According to previous studies, the intrusion scenario is much more critical compared to the groundwater exposure pathway in the case of 239Pu (as well as 226Ra).