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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.
John A. Andersen
Nuclear Technology | Volume 72 | Number 1 | January 1986 | Pages 75-83
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT86-A33755
Articles are hosted by Taylor and Francis Online.
A method is presented for correlating a tracer gas leakage rate to the potential particulate radioactive material (RAM) release from packages for the shipment of RAM, for those cases where a gas leak measurement is used and there is no measurable particulate release. The correlation method involves a calculational technique relating the measured gas leakage to capillary flow, then to the design and dimensions of the actual seal, and then to the minimum size of the particulate material being contained. Numerous examples are cited. This method is useful both in the evaluation of results obtained during regulatory-required testing, and in the process of applying for package certification or licensing. It is indicated that relatively large measured leaks in containment vessels may be analogous to extremely small defects in the actual seal, and to minute releases of RAM.