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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
G. W. Keilholtz, R. E. Moore
Nuclear Technology | Volume 3 | Number 11 | November 1967 | Pages 686-691
Technical Paper and Note | doi.org/10.13182/NT67-A27904
Articles are hosted by Taylor and Francis Online.
The effects of neutron irradiation on poly crystalline α-alumina were investigated. The specimens were translucent solid cylinders of 99.8% of theoretical density with an average grain size of 25 μm. Fast (> 1 MeV) neutron exposures ranged from 0.6 to 5.2 × 1021 n/cm2 where the thermal-to-fast flux ratio varied from 1.6 to 1.1. Temperatures of the specimens were calculated to range from 300 to 600°C. Grain-boundary separation was observed when the neutron dose (> 1 MeV) was approximately 2.3 × 1021 n/cm2, and it became progressively worse with increasing neutron dose. Extensive fracture was observed in specimens exposed to doses above 3 × 1021 n/cm2 (> 1 MeV), but there was virtually no fracturing of samples exposed to doses less than 2 × 1021 n/cm2. Volume of the specimens increased as the neutron dose increased, but the volume as calculated from the lattice parameters, which increased in specimens exposed to a neutron dose of 0.7 × 1021 n/cm2, decreased slightly with additional radiation. Above 0.7 × 1021 n/cm2, the a parameter remained constant while the c parameter decreased. It is suggested that grain-boundary separation, which causes the fracturing of the specimens, is produced by an anisotropic expansion of the crystals produced by defect agglomerates which are too large to affect the lattice parameter measurements.