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.
Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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
Jan 2025
Jul 2024
Latest Journal Issues
Nuclear Science and Engineering
February 2025
Nuclear Technology
January 2025
Fusion Science and Technology
Latest News
Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
L. Väth, Erhard A. Fischer
Nuclear Technology | Volume 71 | Number 1 | October 1985 | Pages 246-257
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33724
Articles are hosted by Taylor and Francis Online.
The fission gas behavior computer model LAKU has been used to analyze annealing experiments performed on thermal reactor fuel and the transient in-pile experiment CABRI All. The results of the calculations revealed some minor weaknesses of the code. Consequently, changes were made in the modeling of the grain boundary gas bubbles, the release of intergranular gas, and the gas behavior in molten fuel. These modeling changes are presented together with the results of the recent calculations.
