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Order-of-convergence study of a condensed-history algorithm implementation

American Nuclear Society - International Conference on Mathematics, Computational Methods and Reactor Physics 2009, M and C 2009

Keith, Rodney L.; Kensek, Ronald P.

An order-of-convergence (with respect to a path-length parameter) verification study is undertaken for an implementation of the condensed-history algorithm in a Monte Carlo electron transport code. "Condensed- history" refers to simulating the cumulative effects of the electron without modeling each individual collision. A 1992 paper by Larsen derived the expected order of convergence for a few mathematical models of this type of algorithm. We examine the order of convergence of a condensed-history algorithm based on that used in the Integrated TIGER Series (as applied to electron albedo problems) in the presence of Monte Carlo uncertainty.

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Fusion transmutation of waste: design and analysis of the in-zinerator concept

Cleary, Virginia D.; Cipiti, Benjamin B.; Guild-Bingham, Avery G.; Cook, Jason T.; Durbin, S.G.; Keith, Rodney L.; Morrow, Charles W.; Rochau, Gary E.; Smith, James D.; Turgeon, Matthew C.; Young, Michael F.

Due to increasing concerns over the buildup of long-lived transuranic isotopes in spent nuclear fuel waste, attention has been given in recent years to technologies that can burn up these species. The separation and transmutation of transuranics is part of a solution to decreasing the volume and heat load of nuclear waste significantly to increase the repository capacity. A fusion neutron source can be used for transmutation as an alternative to fast reactor systems. Sandia National Laboratories is investigating the use of a Z-Pinch fusion driver for this application. This report summarizes the initial design and engineering issues of this ''In-Zinerator'' concept. Relatively modest fusion requirements on the order of 20 MW can be used to drive a sub-critical, actinide-bearing, fluid blanket. The fluid fuel eliminates the need for expensive fuel fabrication and allows for continuous refueling and removal of fission products. This reactor has the capability of burning up 1,280 kg of actinides per year while at the same time producing 3,000 MWth. The report discusses the baseline design, engineering issues, modeling results, safety issues, and fuel cycle impact.

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7 Results
7 Results