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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.
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Metz on Harold Denton: Memories of a life in nuclear safety
A number of years ago, historian and writer Chuck Metz Jr. was at the Bush’s Visitor Center in Tennessee’s Great Smoky Mountains when he ran into former Nuclear Regulatory Commission official Harold Denton and his wife. Metz was at the visitor center, which opened in 2010 and is now a tourist hotspot, because, as he explained to the Dentons at the time, he had overseen the development of its on-site museum and had written a companion coffee-table history book.
The chance meeting turned into a friendship and a fruitful collaboration. Denton, who in 1979 was the public spokesperson for the NRC as the Three Mile Island-2 accident unfolded, had been working on his memoir, but he was stuck. He asked Metz for help with the organization and compilation of his notes. “I was about to retire,” Metz said, “but I thought that exploring the nuclear world might be an interesting change of pace.”
Denton passed away in 2017, but by then Metz had spent many hours with his fast friend and was able to complete the memoir, Three Mile Island and Beyond: Memories of a Life in Nuclear Safety, which was published recently by ANS. Metz shared some of his thoughts about Denton and the book with Nuclear News. The interview was conducted by NN’s David Strutz.
Raphael Craplet, Joonhong Ahn
Nuclear Technology | Volume 177 | Number 3 | March 2012 | Pages 314-335
Technical Paper | Fuel Cycle and Management | dx.doi.org/10.13182/NT12-A13478
Articles are hosted by Taylor and Francis Online.
A mathematical model for mass flow in a generic nuclear fuel cycle was developed. The model can describe various fuel cycle configurations (ranging from once-through to multiple recycling) and reactor types with several regions and batches. It can also be used as a submodel in a regional or global fuel cycle system. Recursive equations for the fuel composition at each point of the cycle were obtained. For specific simplified cases, nonrecursive and equilibrium equations were also derived for compositions, with which the waste reduction ratio was formulated as a function of the system parameters, to show usage of this model for theoretical understanding of the relationship between parameters and performances of the system. A numerical code for this mathematical model was developed. For a simplified equilibrium cycle, sensitivity and constrained optimization of the toxicity reduction ratio with respect to the system parameters were investigated by using the present model and code. It appears that the most important parameter to minimize waste toxicity is the separation efficiency at reprocessing. High fuel enrichment is beneficial because it expands the parametric space within the constraints. Also, depending on the constraints that apply, either the irradiation time or the fraction of core reprocessed at each cycle will be the second most important parameter.