ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.
Robert J. Campana
Nuclear Technology | Volume 12 | Number 2 | October 1971 | Pages 185-193
Technical Paper | Fuel | doi.org/10.13182/NT71-A31026
Articles are hosted by Taylor and Francis Online.
A system has been designed for the gas-cooled fast breeder reactor (GCFR) which equalizes the pressure within the fuel rods with the coolant pressure (85 atm of He) in order to eliminate the possibility of creep collapse of the fuel rods. Additional advantages that result from this design are a shortened core, relaxation of cladding tolerances, low coolant circuit activity, capability of identifying and monitoring leaking fuel elements, safer fuel handling and transport, and potential performance improvements. The system employs in-core charcoal fission-product traps and permits reactor operation with leaking fuel elements. A capsule test of the concept in the ORR has been made and results to date indicate that pressure-equalized fuel is practical and will reduce the development required for the GCFR.