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
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Hangbok Choi, Robert W. Schleicher, John Bolin
Nuclear Technology | Volume 206 | Number 7 | July 2020 | Pages 993-1009
Regular Technical Paper | doi.org/10.1080/00295450.2019.1698936
Articles are hosted by Taylor and Francis Online.
Fuel performance analysis was conducted for the silicon carbide (SiC) composite clad uranium carbide (UC) fuel of a 500-MW(thermal) gas-cooled fast reactor, specifically the energy multiplier module (EM2) under normal operation. The analysis consists of two parts: Part I (this paper) includes a description of design bases and criteria, fuel element design specifications, and material properties and models, while Part II includes the fuel modeling approach, computer code, and fuel design evaluation. In Part I, the design bases and criteria describe the maximum allowed material temperature, cladding stress limit for structural integrity, and cladding strain limit for hermeticity. The material properties and models have been collected from open literature and recent measurements for the UC and SiC composites, respectively. As a result of reviewing legacy UC properties and models, it is recommended to measure the as-fabricated EM2 fuel properties with high priority to the thermal conductivity, swelling rate, and mechanical strength. For the SiC composite cladding, it is recommended to refine the creep rate for its temperature and time dependence. The stress-strain model also needs to be refined for its strain rate, irradiation, and temperature dependence.