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
Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Robert V. Strain, Lawrence A. Neimark, John E. Sanecki
Nuclear Technology | Volume 87 | Number 1 | August 1989 | Pages 187-190
Technical Paper | TMI-2: Materials Behavior / Nuclear Safety | doi.org/10.13182/NT89-A27645
Articles are hosted by Taylor and Francis Online.
Detailed microstructural and microchemical examinations of samples of debris extracted from the lower plenum region of the Three Mile Island Unit 2 reactor were performed using optical and electron-beam instrument microscopy. Results of this study indicate that this material was a previously molten ceramic consisting primarily of UO2 and ZrO2 with smaller amounts of iron, chromium, nickel, and aluminum present also as oxides. The microstructures of the samples were typical of cast multicomponent materials, i.e., rounded grains with additional phases in the grain boundaries. In most cases, the primary grains appeared to be singlephase material as would be expected if a UO2-ZrO2 solid solution were rapidly cooled from the liquid state. However, portions of these grains showed indications of segregation into two distinct phases, and in some areas the whole grains were segregated into two phases. The segregated grains are indicative of a slower cooling rate for part of the material. In addition to the primary urania-zirconia grains, there were large areas of eutectic structure in some of the samples. One of the phases in the eutectic structure consisted of iron and chromium with small amounts of aluminum and nickel, all as oxides. This material was also present in many grain boundaries in the primary grain structure. The grain boundary phase could have a solidus temperature as low as ∼1600K. This low melting point compared to the bulk of the material has led to speculation that the grain boundaries may have remained liquid after the grains themselves had solidified. This would allow the material to flow like wet sand through the structure above the lower plenum at temperatures near or possibly below the melting point of stainless steel (1670 K). At these temperatures, the moving mass would not have severely melted the stainless steel structure near the bottom of the vessel.