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
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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.
Toshiaki Matsuo, Takashi Nishi, Tatsuo Izumida, Masami Matsuda
Nuclear Technology | Volume 125 | Number 3 | March 1999 | Pages 332-336
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT99-A2951
Articles are hosted by Taylor and Francis Online.
The influence of increased temperature from cement hydration was checked on aluminum corrosion prevention when LiNO3 was added to the cement used for aluminum waste cementation.At first, the temperature at the center of a 0.2-m3 cement or mortar form was measured. Then, because the reaction mechanism of LiNO3 involves formation of insoluble LiH 2AlO2 5H2O (Li-Al) preservation film on an aluminum surface, the Li-Al film solubility was measured in a 0.1 M KOH aqueous solution at temperatures from 283 to 353 K. In a second experiment, an aluminum specimen was soaked in a 0.1 M KOH solution with 3 wt% of dissolved LiNO3, and the volume of generated hydrogen gas was measured. Finally, aluminum plates were solidified with mortar in a full-scale test. The mortar mixture contained ordinary portland cement (OPC), blast furnace slag (BFS), and sand with a 1.5 wt% LiNO3 addition, and the volume of generated hydrogen gas was measured.When only OPC was used, the temperature increased to ~363 K. With the BFS and sand addition, this temperature increase was reduced by ~40 to 323 K. The Li-Al film solubility became larger as the temperature of the solution increased. The volume of hydrogen gas generation became large as the temperature increased, especially over 323 K. When the mortar consisted of OPC, BFS, sand, and LiNO3, the volume of hydrogen gas generation from aluminum was reduced, becoming <10% of that without the LiNO3 addition. Thus, it appears that the temperature did not have much influence on the ability of LiNO3 to prevent aluminum corrosion, although the ability was gradually lessened as the temperature increased.