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.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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
Dec 2025
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
December 2025
Nuclear Technology
Fusion Science and Technology
November 2025
Latest News
3D-printed tool at SRS makes quicker work of tank waste sampling
A 3D-printed tool has been developed at the Department of Energy’s Savannah River Site in South Carolina that can eliminate months from the job of radioactive tank waste sampling.
J. R. Fagan, J. O. Mingle
Nuclear Science and Engineering | Volume 18 | Number 4 | April 1964 | Pages 443-447
Technical Paper | doi.org/10.13182/NSE64-A18762
Articles are hosted by Taylor and Francis Online.
The standard analytical approaches to calculating the maximum temperature and surface -heat-flow rate in nuclear reactor fuel plates over-estimates both of these quantities due to the omission of conduction along the axis of the plate. The more general problem, including axial conduction, has been solved for fuel plates in which the clad and meat can be assumed to have the same thermal properties. Calculations made for a natural-circulation reactor show over-estimates of the maximum surface heat flow rate of 4.5 percent and of the maximum temperature rise of 4.8 percent. The error is minimized for systems having a large convection heat-transfer coefficient and will be less than 0.5 percent for most power reactor systems.