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 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Feb 2026
Jul 2025
Latest Journal Issues
Nuclear Science and Engineering
February 2026
Nuclear Technology
January 2026
Fusion Science and Technology
Latest News
DOE, General Matter team up for new fuel mission at Hanford
The Department of Energy's Office of Environmental Management (EM) on Tuesday announced a partnership with California-based nuclear fuel company General Matter for the potential use of the long-idle Fuels and Materials Examination Facility (FMEF) at the Hanford Site in Washington state.
According to the announcement, the DOE and General Matter have signed a lease to explore the FMEF's potential to be used for advanced nuclear fuel cycle technologies and materials, in part to help satisfy the predicted future requirements of artificial intelligence.
P. C. Hall, R. B. Duffey
Nuclear Science and Engineering | Volume 58 | Number 1 | September 1975 | Pages 1-20
Technical Paper | doi.org/10.13182/NSE75-A26763
Articles are hosted by Taylor and Francis Online.
In postulated loss-of-coolant accidents in water-cooled reactors, it is possible for an increase in Zircaloy clad temperature, coupled with reactor depressurization, to give significant local clad strain, and hence reduced area for coolant flow. This paper establishes a simple method of calculating the effect of consequent impairment of local heat-removal capability. An existing flow model, due to Gambill, has been used to estimate the local reduction in the heat transfer coefficient due to clad ballooning. By formulating an energy balance for the fuel pins, temperature transient curves for the distorted cladding are derived from those for undistorted fuel.To analyze the complicated two-phase phenomena, several simplifying assumptions are contained in the flow model. Results, therefore, are given for a range of flow and blockage assumptions, and are shown to be in reasonable accord with an analysis using large and complex computer codes and with all available experimental data.The model can be applied to all types of water-cooled reactors, including pressure tube reactors, by a suitable evaluation of the resistance to bypass flow.