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GLE gets incentives, draft EIS
The governments of Kentucky and McCracken County have granted preliminary approval to Global Laser Enrichment for a comprehensive incentive package to support the development of the North Carolina–based company’s planned Paducah Laser Enrichment Facility in the western part of the state. The performance-based incentive package would provide as much as $98.9 million in tax incentives and other economic incentives—provided that GLE reaches the required thresholds in investments and job creation.
In addition, the Nuclear Regulatory Commission, in cooperation with the U.S. Army Corps of Engineers, has completed a draft environmental impact statement (EIS) in response to GLE’s application to construct and operate the PLEF. Members of the public can submit comments on the draft EIS by May 11 for consideration by the NRC.
C. P. Marcel, M. Rohde, T. H. J. J. Van der Hagen
Nuclear Technology | Volume 164 | Number 2 | November 2008 | Pages 232-244
Technical Paper | Reactor Safety | doi.org/10.13182/NT08-A4022
Articles are hosted by Taylor and Francis Online.
The stability performance of the Economic Simplified Boiling Water Reactor (ESBWR) is studied with the downscaled GENESIS facility. The GENESIS design is based on fluid-to-fluid modeling and includes an artificial void reactivity feedback system for simulating the neutronic-thermal-hydraulic coupling. The experiments show that the ESBWR thermal-hydraulic oscillatory mode is very stable at nominal conditions, exhibiting a decay ratio DR = 0.12 and a remarkably low resonance frequency fres = 0.11 Hz. This result indicates a static pressure head-driven phenomenon since this frequency corresponds well to typical frequencies found for density wave oscillations traveling through the core plus chimney sections. For the reactor-kinetic oscillatory mode, we found a decay ratio DR = 0.30 and a resonance frequency fres = 0.75 Hz. This corresponds well to density wave oscillations traveling through the core indicating the instability mechanism is driven by the interplay between the core friction and the neutronic response due to void changes in the core. By comparing these results with those obtained with the TRACG computational code, it was found that they agree very well. In addition, the stability performance of the thermal-hydraulic and the reactor-kinetic mode is investigated for a wide range of conditions, confirming the existence of large margins to instabilities of the ESBWR design.