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
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
B. L. Harbourne, M. S. Beck, J. P. Foster, A. Biancheria
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 156-170
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31183
Articles are hosted by Taylor and Francis Online.
An LMFBR fuel rod performance analysis system has been developed using the CYGRO-F computer code. The approach used was to model materials properties and phenomena using basic data and fundamental formulations as far as possible. Lack of data and understanding prevent a completely fundamental solution. The uncertainties were resolved by normalizing the code against selected experimental results and making appropriate adjustments to the models. The result of this work is an analytical system of models integrated into a central stress-strain analysis. Application of the system to independent experimental data gave satisfactory agreement between analysis and observation. Four highly significant models have emerged from this work. The analytical fuel swelling model simulates volume increase saturation and subsequent volume conservate growth which can result in center-hole growth independent of pore migration. The feasibility of a fundamental fuel swelling model has been demonstrated. This model describes the nucleation, growth, and migration of gas bubbles and produces mechanical effects similar to those in the analytical model. The cladding swelling model accounts for the effects of stress on swelling rate to reproduce the large volume changes observed in some fuel rod cladding. The results of this model are in qualitative agreement with fundamental analyses of the effect. Studies of startup and early life behavior resulted in a thermomechanical analysis system which describes in detail the complex interacting phenomena occurring under these transient conditions. The system may be applied to the determination of LMFBR core limiting operating conditions.