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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.
J. Vrijen, J. K. van Westenbrugge, L. van der Wiel, P. L. F. Rademakers, C. P. Scheepens, J. W. Schinkel
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 250-258
Technical Paper | Materials | doi.org/10.13182/NT55-250
Articles are hosted by Taylor and Francis Online.
The design lifetime of the steam generators for the SNR-300 is 100 000 h. For the steam generators of the next SNR generation, this design lifetime has been increased to 300 000 h. This prevents the application of the current structural material, a niobium stabilized Cr—1 Mo and started a materials selection process based on the primary requirement of a high creep strength. Other important criteria in this selection process have been a high yield stress at design temperature, adequate ductility, good corrosion resistance in liquid sodium, water, and steam, and acceptable manufacturing properties. This resulted in the selection of the high alloy steel ×20CrMo12 1 (12% Cr, 1% Mo) as prime candidate material. This material has been subjected to an optimization program with regard to its mechanical properties and to a determination of its susceptibility to stress corrosion at high temperatures. It has been demonstrated that this type of steel shows a rather strong influence of tempering treatment and thermal aging on its strength and impact ductility, especially in the heat-affected zone of welded joints. The material shows a mixed transgranular-intergranular corrosion attack only under severe corrosive conditions in FeCl2 solutions under high mechanical stress. High tempering temperatures and electroslag remelting have a beneficial influence on impact ductility as well as on the corrosion susceptibility.