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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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.