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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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
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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.
Andrew Richard Raymond Telford
Nuclear Technology | Volume 56 | Number 1 | January 1982 | Pages 33-39
Technical Paper | Fission Reactor | doi.org/10.13182/NT82-A32878
Articles are hosted by Taylor and Francis Online.
Tests have been carried out on one of the advanced gas-cooled reactors (AGRs) at Hinkley Point to determine the fuel temperature coefficient of reactivity, an important safety-related parameter. Reactor neutron flux was measured during transients induced by movement of a bank of control rods from one steady position to another. An inverse kinetics analysis was applied to the recorded flux transient to determine the reactivity change as the fuel temperature changed, and the variation of mean fuel temperature was derived from the flux transient by a multiplane thermal-hydraulics code representing an AGR fuel channel The fuel temperature coefficient was then obtained from the slope of a plot of core reactivity against fuel temperature. The uncertainty to be applied to the derived temperature coefficient has been shown to be approximately ±10% at the one standard deviation level The experimental technique has been found to be simple to apply on a commercial reactor and has given consistent results over a range of reactor operating conditions. Calculations of fuel temperature coefficients of reactivity (based on the lattice code, ARGOSY) have been carried out and reactor averaged values deduced for comparison with experiment. The calculated and measured coefficients agree to within one standard deviation over a range of core irradiations and power levels.
