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
April 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
IAEA project aims to develop polymer irradiation model
The International Atomic Energy Agency has launched a new coordinated research project (CRP) aimed at creating a database of polymer-radiation interactions in the next five years with the long-term goal of using the database to enable machine learning–based predictive models.
Radiation-induced modifications are widely applicable across a range of fields including healthcare, agriculture, and environmental applications, and exposure to radiation is a major factor when considering materials used at nuclear power plants.
Dennis R. Coleman
Nuclear Technology | Volume 46 | Number 2 | December 1979 | Pages 213-219
Technical Paper | Nuclear Power Reactor Safety (Presented at the ENS/ANS International Meeting, Brussels, Belgium, October 16–19, 1978) / Reactor | doi.org/10.13182/NT79-A32319
Articles are hosted by Taylor and Francis Online.
The results of power ramp tests and associated cladding failure calculations performed as part of FRAP-T4 independent assessment studies have been analyzed. The 90 ramp tests considered are characterized in terms of relevant fuel design and operating parameters for Zircaloy-clad UO2 fuel rods. The use of alternative gap closure and fuel deformation models strongly affects results of the current stress-dependent failure probability model. The influence of both mechanical and chemical failure mechanisms can be separated to some extent by interpreting the concurrent effects of both the ramp-induced stress levels and the relative amounts of retained fission gas available for promoting stress corrosion. A relatively simple modeling approach can meet the basic mechanistic requirements for calculating pellet-cladding interaction failure probability.