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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
J. F. Lagedrost, D. F. Askey, V. W. Storhok, J. E. Gates
Nuclear Technology | Volume 4 | Number 1 | January 1968 | Pages 54-61
Technical Paper and Note | doi.org/10.13182/NT68-A26353
Articles are hosted by Taylor and Francis Online.
The thermal conductivity of PuO2 as determined by thermal diffusivity measurements is presented for the temperature range 250 to ≈1200°C. Specimens of PuO2 with confirmed stoichiometry were fabricated by hot isostatic pressing of powder to densities of 96.5 and 81.9% of theoretical. The thermal diffusivity of four specimens, two of each density, was measured by the heat pulse technique using a laser as the heat source. The data indicated that the thermal conductivity of PuO2 is lower than that of UO2, and decreases with increasing temperature from 250 to 1000°C in an approximate 1/T relation. Values range from 0.06 W/(cm deg C) at 300°C to 0.025 W/(cm deg C) at 1200°C. An apparent reduction of the PuO2 was observed at temperatures above 1200°C.
