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NRC approves TerraPower construction permit
Today, the Nuclear Regulatory Commission announced that it has approved TerraPower’s construction permit application for Kemmerer Unit 1, the company’s first deployment of Natrium, its flagship sodium fast reactor.
This approval is a significant milestone on three fronts. For TerraPower, it represents another step forward in demonstrating its technology. For the Department of Energy, it reflects progress (despite delays) for the Advanced Reactor Demonstration Program (ARDP). For the NRC, it is the first approval granted to a commercial reactor in nearly a decade—and the first approval of a commercial non–light water reactor in more than 40 years.
Pedro B. Macedo, Aaron Barkatt, Barbara C. Gibson, Charles J. Montrose
Nuclear Technology | Volume 73 | Number 2 | May 1986 | Pages 199-209
Technical Paper | Performance of Borosilicate Glass High-Level Waste Forms in Disposal System / Radioactive Waste Management | doi.org/10.13182/NT86-A33784
Articles are hosted by Taylor and Francis Online.
Evaluating the durability of nuclear waste glass material in terms of leach test results requires that one make reasonable extrapolations from laboratory experiments performed over a few years’ duration to repository behavior over time scales ranging up to tens of thousands of years. These require an understanding of the mechanisms that govern the leaching of glass as well as an accompanying predictive capability. By comparing the measured behavior with the predictions of mechanistic models, it can be concluded that at high flow rates, kinetic factors are predominant, while at low flow rates, saturation of the aqueous medium with respect to major matrix elements, particularly with respect to silica present in the glass and in its alteration products, becomes a controlling factor. A mathematical framework in which this synthesized picture can be expressed is presented. A careful analysis of the situation indicates that under likely repository conditions the fractional annual release rates can be expected to fall below the U.S. Nuclear Regulatory Commission criterion of 10−5 yr−1.