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
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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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.
C. C. Lin, C. R. Pao, J. S. Wiley, W. R. DeHollander
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 253-265
Technical Paper | Fission Reactor | doi.org/10.13182/NT81-A32770
Articles are hosted by Taylor and Francis Online.
A mathematical model of corrosion product transport in the boiling water reactor (BWR) primary system has been developed. The model, which can be characterized as a semi-empirical phenomenological model, is capable of reproducing the observed data obtained in many BWRs with a variety of operational histories and a wide range of radiation levels. The results of parametric studies confirm the successful experience that the radiation fields in operating plants can be controlled and reduced by close control of the water quality in the primary system. The radiation field measured at recirculation piping of a new plant can be controlled below 200 mR/h over its entire plant life.
