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
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
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.
Chung-Yi Wang
Nuclear Technology | Volume 51 | Number 3 | December 1980 | Pages 332-348
Technical Paper | Mechanics Applications to Fast Breeder Reactor Safety / Reactor | doi.org/10.13182/NT80-A32571
Articles are hosted by Taylor and Francis Online.
An implicit finite difference method has been developed and incorporated into the ICECO code for analyzing hydrodynamics in the above-core region induced by the upper internal structure, and sodium spillage through penetrations and ruptured seals resulting from slug impact on the reactor cover. Eulerian description is employed so that flow through coolant passageways, large material distortions, two-dimensional sliding interfaces, flow around corners, and out-flow boundary conditions can be easily treated. In the analysis, the upper internals and the reactor cover are considered as perforated structures. A control-volume technique is utilized for deriving equations for the conservation of mass, momentum, and energy. The basic idea is to use actual fluid volume and actual flow areas in the mathematical formulation. Several modified Poisson equations are obtained, which govern the hydrodynamic pressures in the vicinity of the perforated structures. Sample problems are provided to illustrate the code capabilities in assessing the effect of the upper internal structure on the containment response and in estimating the amount of coolant ejected from the primary containment.