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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Peter J. Jensen, Kent D. Richert, Jason Chao
Nuclear Technology | Volume 76 | Number 2 | February 1987 | Pages 290-302
Fourth International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT87-A33882
Articles are hosted by Taylor and Francis Online.
A RETRAN-02 analysis was performed for a loss-of-feedwater transient without scram for a Westinghouse four-loop plant with Series 51 steam generators. A goal of this study was to use the same plant parameters that were used by Westinghouse in a report issued in December 1979. The primary differences in results from the two studies can be attributed to differences in the two methodologies. Sensitivity of the primary pressure response to steam generator nodalization, turbine trip time, moderator reactivity feedback coefficients, and Doppler reactivity coefficients was also studied.