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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.
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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
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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.
N. P. Bhat, Hans U. Borgstedt
Fusion Science and Technology | Volume 21 | Number 1 | January 1992 | Pages 52-59
Technical Paper | Blanket Engineering | doi.org/10.13182/FST92-A29705
Articles are hosted by Taylor and Francis Online.
Electrochemical oxygen meters with yttrium-doped thoria, yttrium-stabilized zirconia, and calcium-stabilized zirconia solid electrolytes are tested for the measurement of oxygen activity in Pb-17Li eutectic alloy, the proposed breeder blanket fluid for fusion reactors. The oxygen potentials of the alloy measured by these three meters are compared with the oxygen potentials of the alloy after the addition of lithium oxide and with theoretical values. Zirconium and yttrium metal foils are tested for gettering oxygen from the alloy. The compatibility of the three ceramic materials in the liquid alloy and the stability of the meters for prolonged use are discussed. The influence of oxygen on the corrosion of steels in Pb-17Li is reviewed in light of the oxygen potentials of the alloy compared to thermodynamic data of the ternary oxides of the metal constituents of steels. The possibility of using the oxygen meters to measure the lithium activity of the alloy is also indicated.
