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
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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!
Latest Magazine Issues
May 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
Latest News
NRC v. Texas: Supreme Court weighs challenge to NRC authority in spent fuel storage case
The State of Texas has not one but two ongoing federal court challenges to the Nuclear Regulatory Commission that could, if successful, turn decades of NRC regulations, precedent, and case law on its head.
R. Godesar, M. Guyette, N. Hoppe
Nuclear Technology | Volume 9 | Number 2 | August 1970 | Pages 205-217
Fuel Performance Model | Symposium on Theoretical Models for Predicting In-Reactor Performance of Fuel and Cladding Material | doi.org/10.13182/NT70-A28809
Articles are hosted by Taylor and Francis Online.
The COMETHE II computer program has been formulated to predict the thermal and mechanical behavior of fuel pins during their irradiation life. It calculates, in particular, the temperature distribution, the radial and axial fuel swelling and expansion, the fission gas release, and the stresses and strains in the cladding. The program involves many models for this purpose. Some of these have been separately tested and calibrated with respect to available experimental results in the literature. Calibration of the whole program is also being currently performed. COMETHE II results are compared with experimental data for different burnups and thermal ratings. The agreement obtained with the experiments is rather good, the theoretical data lying generally in the margin of error of the experimental data. The capabilities of the COMETHE II program are illustrated by a parametric study of the gap width influence on the maximum center temperature and on the strain of the sheath. This example shows that the COMETHE II program is a useful tool for the design of fuel pins for fast or thermal power reactors.