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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
W. Bixby, K. Almenas
Nuclear Technology | Volume 23 | Number 3 | September 1974 | Pages 213-221
Technical Paper | Reactor | doi.org/10.13182/NT74-A15914
Articles are hosted by Taylor and Francis Online.
Spatial neutron flux distributions have been measured in large volumes (450 liters) of several gaseous media. Measurements were made in nearly pure CO2 having a σs/σc ratio of ∼1200 and in mixtures of BF3 and CO2 with σs/σc ratios down to ∼0.02. Thus, distributions were obtained in an almost purely scattering and purely absorbing medium. The experimental results have been processed to represent the flux distribution in a semi-infinite medium of identical composition. This required removal of the leakage component, a correction made possible because the neutron mean-free-path of the measured media differed by several orders of magnitude. In effect, distributions determined almost entirely by neutron leakage and distributions determined almost entirely by neutron capture were directly measured. The experimental results were compared with transport theory calculational models by using several assumptions concerning the angular distribution of the neutron source flux. Satisfactory agreement was achieved between the experimental and analytical results when a purely collimated incident flux was assumed.