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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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Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Donald G. Schweitzer, Cesar A. Sastre
Nuclear Technology | Volume 86 | Number 3 | September 1989 | Pages 305-312
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT89-A34298
Articles are hosted by Taylor and Francis Online.
At present, only one concept, the Swedish design utilizing a thick-walled copper waste package, has been accepted as being capable of isolating high-level waste for hundreds of thousands of years in a granite-type repository. Theoretical arguments show that after the relatively short times required for salt consolidation selfshielded thin-walled copper waste packages have no significant failure or degradation reactions in anoxic neutral and acid brines. Thermodynamic analyses of reactions after consolidation (constant-volume reactions under lithostatic pressures in the absence of oxygen) show that miniscule amounts of metal reacting with brine can produce very large hydrogen pressures. For copper waste packages, almost no consumption of copper is required to produce the small equilibrium hydrogen pressure needed to prevent reaction. Reaction under these conditions no longer depends on poorly understood corrosion mechanisms, but results from hypothetical mechanisms that allow the equilibrium hydrogen to migrate away from the waste package. Analyses of gamma radiolysis and diffusion processes show that in an array of thousands of waste packages removal of hydrogen from the outer packages should be negligible for a properly selected salt repository.