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
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
Feb 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
March 2025
Nuclear Technology
Fusion Science and Technology
February 2025
Latest News
Candidates for leadership provide statements: ANS Board of Directors
With the annual ANS election right around the corner, American Nuclear Society members will be going to the polls to vote for a vice president/president-elect, treasurer, and members-at-large for the Board of Directors. In January, Nuclear News published statements from candidates for vice president/president-elect and treasurer. This month, we are featuring statements from each nominee for the Board of Directors.
R. C. Noyes, P. K. Doherty, S. A. Caspersson, N. Hanus, D. W. Stuteville
Nuclear Technology | Volume 26 | Number 4 | August 1975 | Pages 460-471
Technical Paper | Fuel | doi.org/10.13182/NT75-A24446
Articles are hosted by Taylor and Francis Online.
A study to determine the optimum pin diameter for carbide fuel in a liquid-metal fast breeder reactor was made. Several subsidiary parameters, including coolant velocity, burnup, and properties of the clad and subassembly duct material, were studied for their effect on the optimum pin diameter. The materials used in the analysis were Type 316 stainless steel and a high strength, low swelling material capable of operation to a damage fluence of 3.6 × 1023 n/cm2. Using doubling time and fuel cycle cost as the basis for judgment, an optimum pin outer diameter (o.d.) range of 0.37 to 0.40 in. was found for both the near-term and advanced structural materials. Because of practical limits of the Fast Test Reactor testing, an o.d. of 0.37 in. is recommended. The optimum pin diameter was found to be independent of fuel burnup. From a doubling time point of view, no incentive was found for development of carbide fuel with a burnup greater than 80 to 90 MWd/kg.