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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Colin Judge: Testing structural materials in Idaho’s newest hot cell facility
Idaho National Laboratory’s newest facility—the Sample Preparation Laboratory (SPL)—sits across the road from the Hot Fuel Examination Facility (HFEF), which started operating in 1975. SPL will host the first new hot cells at INL’s Materials and Fuels Complex (MFC) in 50 years, giving INL researchers and partners new flexibility to test the structural properties of irradiated materials fresh from the Advanced Test Reactor (ATR) or from a partner’s facility.
Materials meant to withstand extreme conditions in fission or fusion power plants must be tested under similar conditions and pushed past their breaking points so performance and limitations can be understood and improved. Once irradiated, materials samples can be cut down to size in SPL and packaged for testing in other facilities at INL or other national laboratories, commercial labs, or universities. But they can also be subjected to extreme thermal or corrosive conditions and mechanical testing right in SPL, explains Colin Judge, who, as INL’s division director for nuclear materials performance, oversees SPL and other facilities at the MFC.
SPL won’t go “hot” until January 2026, but Judge spoke with NN staff writer Susan Gallier about its capabilities as his team was moving instruments into the new facility.
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.