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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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February 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Fermilab center renamed after late particle physicist Helen Edwards
Fermi National Accelerator Laboratory’s Integrated Engineering Research Center, which officially opened in January 2024, is now known as the Helen Edwards Engineering Center. The name was changed to honor the late particle physicist who led the design, construction, commissioning, and operation of the lab’s Tevatron accelerator and was part of the Water Resources Development Act signed by President Biden in December 2024, according to a Fermilab press release.
H. E. Khalifa, C. P. Deck, K. C. Chen, C. A. Back
Fusion Science and Technology | Volume 61 | Number 1 | January 2012 | Pages 375-380
Materials | Proceedings of the Fifteenth International Conference on Emerging Nuclear Energy Systems | doi.org/10.13182/FST12-A13448
Articles are hosted by Taylor and Francis Online.
Chemical vapor infiltrated (CVI) silicon carbide fiber reinforced-silicon carbide matrix (SiC-SiC) composite is a relatively new material and has come under increased scrutiny as an attractive material for nuclear applications. In these materials, the interplay between fiber and matrix leads to enhanced fracture toughness. However, due to the inherent directionality of the fibers, under-standing the mechanical and thermal performance is complex and requires careful characterization. At General Atomics, a laboratory has been established to develop these materials for a range of applications, in particular for the Energy Multiplier Module (EM2), which is a gas-cooled fast reactor.In this paper, the program of work that is being undertaken to fabricate and characterize SiC matrix com-posites is discussed. For mechanical testing, specialized fixtures have been developed to hold the thin ceramic composite specimens. For thermal testing, the purge gas species and flow rate have been identified as important parameters. Initial results on planar samples have been performed on SiC-SiC samples and hot pressed SiC samples.