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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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
Mar 2024
Jan 2024
Latest Journal Issues
Nuclear Science and Engineering
April 2024
Nuclear Technology
Fusion Science and Technology
February 2024
Latest News
Kentucky legislature sends nuclear bills to governor
Kentucky’s Republican-majority legislature passed a bill this past week that could bring nuclear energy to the “coal-is-king” state as lawmakers broadly seek solutions to reduce carbon emissions. The bill went to Democratic Gov. Andrew Beshear on Monday for final approval.
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.