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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
Aug 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
September 2025
Nuclear Technology
Fusion Science and Technology
August 2025
Latest News
New coolants, new fuels: A new generation of university reactors
Here’s an easy way to make aging U.S. power reactors look relatively youthful: Compare them (average age: 43) with the nation’s university research reactors. The 25 operating today have been licensed for an average of about 58 years.
M. Ishii, T. C. Chawla
Nuclear Science and Engineering | Volume 56 | Number 2 | February 1975 | Pages 188-195
Technical Paper | doi.org/10.13182/NSE75-A26657
Articles are hosted by Taylor and Francis Online.
The formation of hot spots in fuel cladding due to the deposition of a low-conductivity heat-generating fuel or due to fission-gas-jet impingement is a very credible event and can significantly influence the probability for slow fuel-failure propagation in a subassembly of a liquid-metal fast breeder reactor. By assuming steady-state conditions, a general expression is obtained for the temperature distribution in these hot spots. As special cases, expressions are obtained for temperature distributions in hot spots caused by fission-gas-jet impingement and partial or total channel blockages by fuel debris. A partial verification of the model for thermal analysis is provided by comparing predictions for the temperature distribution in the gas-jet impingement region to the available experimental data.