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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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.
Jozef C. Domanus
Nuclear Technology | Volume 92 | Number 3 | December 1990 | Pages 389-395
Technical Paper | Radiation Application | doi.org/10.13182/NT90-A16240
Articles are hosted by Taylor and Francis Online.
The importance of measuring dimensions from neutron radiographs of nuclear reactor fuel is explained. Measurements are taken using either a profile projector or a traveling microdensitometer. Neutron radiographs are made by the direct, transfer, and track-etch techniques, the last two being used for radioactive objects such as spent reactor fuel. The accuracy of these measurements was investigated during the Euratom Neutron Radiography Working Group Test Program. Measuring results are discussed for different kinds of nuclear fuel pin dimensions and 30 different combinations of recording materials. The accuracy of the measurements is assessed by calculating standard deviations between the dimensions determined from neutron radiographs and the true dimensions of a calibration fuel pin.