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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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.
C. M. Sommer, W. M. Stacey, B. Petrovic
Nuclear Technology | Volume 172 | Number 1 | October 2010 | Pages 48-59
Technical Paper | Fuel Cycle and Management | dx.doi.org/10.13182/NT10-A10881
Articles are hosted by Taylor and Francis Online.
A fuel cycle analysis was performed for the SABR transmutation reactor concept, using the ERANOS fast reactor physics code. SABR is a sodium-cooled, transuranic (TRU)-Zr-fueled, subcritical fast reactor driven by a tokamak fusion neutron source. Three different four-batch reprocessing fuel cycles, in which all the TRUs from spent nuclear fuel discharged from light water reactors are fissioned to >90% (by recycling four times), was examined. The total fuel residence time in the reactor was limited in these three cycles by a radiation damage limit (100, 200, or 300 displacements per atom) to the cladding material. In the fourth cycle the fuel residence time was determined by trying to achieve 90% burnup in a once-through cycle without reprocessing.