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Metz on Harold Denton: Memories of a life in nuclear safety
Metz
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.
Tsuguyuki Kobayashi
Nuclear Technology | Volume 177 | Number 2 | February 2012 | Pages 231-244
Technical Paper | Reprocessing | dx.doi.org/10.13182/NT12-A13368
Articles are hosted by Taylor and Francis Online.
A simple procedure to simulate the important kinetic features of counter-current processes in pulsed columns has been developed. The overall mass transfer coefficient was simplified to be constant along the column, and the stripping of Pu4+ by hydroxylamine is assumed to be instantaneous to avoid complex reaction rate calculations. The number of calculation cells can be determined by making calculations with an increasing number of cells until its influence becomes small enough. The validity of these simplifications was confirmed by comparing the calculation results with a wide range of measured data from extraction and stripping as well as Pu partition tests with laboratory, engineering, and pilot scale columns. This procedure is intended for use in a conceptual design study of a future fast breeder reactor (FBR) reprocessing plant. An example of its application in a flow sheet calculation was demonstrated, where a coextraction process of U and Pu was simulated to find the conditions to obtain a solution with Pu/(U + Pu) ratio being 30% from a typical feed of FBR spent fuel solution.
