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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
Meeting Spotlight
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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!
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Latest News
NEI chief executive highlights “unlimited potential” for nuclear in state of the industry address
Korsnick
In the Nuclear Energy Institute’s annual State of the Nuclear Energy Industry report, NEI president and CEO and Maria Korsnick expressed optimism about the nuclear industry and she issued a call to action.
Her address was part of NEI’s Nuclear Energy Policy forum. The forum, being held in Washington, D.C., on May 20 and May 21, brings together industry leaders, policy stakeholders, and clean energy experts to discuss nuclear advocacy. Korsnick’s remarks focused on the private capital flowing into the industry, progress on regulatory reform and new nuclear technology, and how the U.S. is trying to take the lead on the global nuclear stage.
“We are here at an unprecedented time in our industry history,” Korsnick said. “I’m proud to say that the nuclear industry has a future of unlimited potential.”
J. Rest
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 553-564
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32914
Articles are hosted by Taylor and Francis Online.
The interrelationship between fuel fracturing (microcracking), temperature scenario, and fission-gas-bubble response is investigated. The fission-gas-bubble behavior is described using the FASTGRASS computer code. A model, based on the work of DiMelfi and Deitrich describing ductile/brittle fuel behavior, has been incorporated into the FASTGRASS analysis. The predictions of fission-gas release, radial distribution of released gas, radial distribution of microcracking, and fuel temperatures are compared with the results of transient direct-electrical-heating experiments on irradiated light water reactor fuel. Finally, results of analyses for Three Mile Island Unit 2 type accident conditions are presented and implications for microcracking and fission-gas behavior during this accident are discussed.