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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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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.
G. D. Wait
Nuclear Technology | Volume 4 | Number 6 | June 1968 | Pages 440-447
Technical Paper and Note | doi.org/10.13182/NT68-A26370
Articles are hosted by Taylor and Francis Online.
A high-sensitivity dosimeter system was developed to measure low gamma-ray dose rates in the presence of neutrons. The detector is a liquid scintillator that employs hexafluorobenzene (C6F6) as a solvent and is practically hydrogen free. The energy absorbed in the scintillator is determined directly by counting the analog-to-digital converter pulses of a multichannel analyzer in a fast scaler. The ratio of energy absorbed to air exposure dose was measured for incident gamma energies of 0.06 MeV (241Am), 0.66 MeV (137Cs), 1.25 MeV(60Co), and 4.43 MeV (241AmBe) and gave an average deviation of 3.5% from a constant ratio of energy absorbed to air exposure. A Monte Carlo computer program was written to determine the response of the scintillator to a broader range of gamma-ray energies. This indicated that the ratio of the energy absorbed to the air exposure would vary within the limits of ±10% from 50keV to 10 MeV. The response to fast neutrons also was measured and compared with calculations which showed that the major component in the neutron response was produced by β− decay following the (n,α) reaction in 19F. For the broad spectrum of incident fast neutrons (up to 11.5 MeV) from a 241AmBe source, the neutron response of the dosimeter was found to be < 8% of its response to the comparable flux of 4.43 MeV gamma rays from the source.