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
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
March 2026
Nuclear Technology
February 2026
Fusion Science and Technology
April 2026
Latest News
MARVEL PDSA approval could serve as blueprint
MARVEL, the Microreactor Applications Research Validation and Evaluation project at Idaho National Laboratory, has had its preliminary documented safety analysis approved by the Department of Energy, marking a milestone in its development and serving as a potential outline for other microreactors in development.
G. Bandyopadhyay
Nuclear Technology | Volume 40 | Number 1 | August 1978 | Pages 62-78
Technical Paper | Fuel | doi.org/10.13182/NT78-A26700
Articles are hosted by Taylor and Francis Online.
To evaluate the role of fission gas in hypothetical core disruptive accidents, experimental and analytical information describing the fission gas behavior in rapid temperature transients is urgently needed. In the present work, a direct-electrical-heating apparatus was used to obtain information on the fission gas behavior and the response of mixed-oxide fuel elements to simulated thermal transient conditions. The experimental results indicate that fission gas response and swelling behavior are strongly dependent on the transient heating rate, and that fission gas can contribute significantly to the failure of a fuel stack during a temperature transient. The microstructural results from these tests were subsequently used to perform a limited verification of the fission gas release and swelling code, FRAS, which was developed to describe the fission gas release behavior in rapid temperature transients. A comparison of the measured intragranular bubble sizes (and in some cases bubble densities) with the calculated bubble sizes (and densities) revealed that the current version of the FRAS code is inadequate in some transient conditions. A nonequilibrium analysis of bubble coalescence may be necessary to describe the fission gas behavior in such temperature transients.