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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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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.
J. P. Moore, R. S. Graves, D. L. McElroy
Nuclear Technology | Volume 22 | Number 1 | April 1974 | Pages 88-93
Technical Paper | Fusion Reactor Materials / Material | doi.org/10.13182/NT74-A16277
Articles are hosted by Taylor and Francis Online.
The thermal conductivity λ, electrical resistivity ρ, and absolute Seebeck coefficient S of two grades of nearly isotropic graphite were measured from 300 to 1000°K both before and after neutron irradiation up to 5.0 × 1021 n/cm2 (>50 keV). Nominal irradiation temperatures were 823, 923, and 1023°K. The thermal resistance, λ−1, of the unirradiated graphites was proportional to T from 500 to 1000°K. Neutron irradiation decreased λ at 300°K by a factor of 4.5 and increased ρ at 300°K by 2.5, in general agreement with previous investigations, and irradiation changed S from small negative values to large positive ones. The product of thermal conductivity and electrical resistivity was nearly constant with fluence from 2.6 × 1021 to 5.0 × 1021 n/cm2.
