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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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May 2025
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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.
Tyler R. Steiner, Richard H. Howard
Nuclear Technology | Volume 208 | Number 11 | November 2022 | Pages 1745-1755
Technical Paper | doi.org/10.1080/00295450.2022.2072652
Articles are hosted by Taylor and Francis Online.
A high-temperature, steady-state, in-pile experiment was developed to simulate prototypical nuclear thermal propulsion conditions. The experimental development of the resistively heated test apparatus involved spatially scaling the device to a larger heated region from a previous smaller out-of-pile prototype. A series of tests and investigations were conducted to replicate the smaller out-of-pile system’s success of achieving 2500 K. However, limitations within the larger assembly were identified; specifically, the heater filament design does not scale well. The larger assembly can reliably generate usable temperature levels from room temperature up to those exceeding 1300 K for hours. It can briefly sustain a usable 1800 K. The larger system is achieving temperatures over 2500 K, but these are localized and unable to be monitored in the current design. The achieved temperature levels remain suitable for testing various components considered for a nuclear thermal rocket. However, due to the limitations of the current heater filament, it is recommended that the apparatus be redesigned to utilize a rigid heating element similar to that used during the Radioisotope Propulsion Technology Program (Project POODLE) in the 1960s.