ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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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June 2025
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May 2025
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.
Dennis G. Vasilik, Richard L. Murri, George P. Fisher
Nuclear Technology | Volume 14 | Number 3 | June 1972 | Pages 279-283
Technical Paper | Instrument | doi.org/10.13182/NT72-A31117
Articles are hosted by Taylor and Francis Online.
Neutron radiography studies have been conducted using an accelerator source of 14.3 ± 0.3 MeV neutrons and a water moderator. The yield of the accelerator was 6.18 × 101 n/sec. The peak thermal-neutron flux of the system was measured to be 6.87 × 107 n/(cm2 sec) at 5.1 cm from the source. A cadmium ratio of 3.4 was measured at this position. A theoretical two-group analysis of the thermal-neutron flux distribution was also performed. The experimental data verified the theoretical results. Neutron multiplication experiments were also conducted by bombarding a 238U target surrounded by the water moderator. It was experimentally determined that 2.5 cm of 238U yielded a maximum multiplication factor of 2.5.
