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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.
Gérard Ducros
Nuclear Technology | Volume 68 | Number 3 | March 1985 | Pages 370-384
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT85-A33582
Articles are hosted by Taylor and Francis Online.
Within the framework of nondestructive inspection of irradiation rigs carried out in the pool of the 35-MW Siloe reactor in Grenoble, transverse gamma scanning has been developed. It permits radial distribution of the fission products in irradiated fuels to be determined and, therefore, considerable improvement to be made in the knowledge of their behavior. A new method of transverse measurement treatment has recently been elaborated: the ISARD program reconstructs the distribution of gamma emitters in a section of the fuel pin from several scans carried out under different incidences. The algorithm is built on a combination of two iterative methods and allows a limited number of projections to be used without assuming any particular symmetry, taking the selfattenuation of gamma rays in the fuel element and their absorption by the rig walls into account. The ISARD program has been qualified experimentally, using a sample composed of various materials activated in the reactor. The sample and the irradiation were designed to simulate a large number of different distributions of gamma emitters (i.e., activation products), similar to typical repartitions of fission products in a fuel pin (peripheral or central concentrations, local accumulation or voids . . . ). This qualifying study, treated parametrically, allowed practical choices to be made as to the routine application of the method to irradiated fuel pins.