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Nuclear Technology Volume 184, 2013 - Issue 1
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Technical Paper

A Stylized Three-Dimensional Pressurized Water Reactor Benchmark Problem with UO2 and MOX Fuel

Farzad RahnemaGeorgia Institute of Technology, Nuclear and Radiological Engineering/Medical Physics Programs, George W. Woodruff School, Atlanta, Georgia 30332-0405
,
Ryan HonGeorgia Institute of Technology, Nuclear and Radiological Engineering/Medical Physics Programs, George W. Woodruff School, Atlanta, Georgia 30332-0405
&
Steven DouglassGeorgia Institute of Technology, Nuclear and Radiological Engineering/Medical Physics Programs, George W. Woodruff School, Atlanta, Georgia 30332-0405
Pages 1-28 | Published online: 20 Mar 2017

References

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  • S. CATHALAU, J. C. LEFEBVRE, and J. P. WEST, “Proposal for a Second Stage of the Benchmark on Power Distributions within Assemblies,” NEA/NSC/DOC(96)2 (1996).
  • T. KOZLOWSKI and T. J. DOWNAR, “OECD/NEA and U.S. NRC PWR MOX/UO2 Core Transient Benchmark,” NEA/NSC/DOC(2003)20 (Aug. 2003).
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  • J. E. HOOGENBOOM, W. R. MARTIN and B. PETROVIC, “Monte Carlo Performance Benchmark for Detailed Power Density Calculations in a Full Size Reactor Core,” Benchmark Specifications Revision 1.2, July 2011; http://www.nea.fr/dbprog/MonteCarloPerformanceBenchmark.htm (2010)(cur-rent as of Nov. 7, 2011).
  • T. SIMEONOV, “Release Notes-Helios System Version 1.8,” StudsvikScandpower Report, SSP-03/221 (Nov. 26, 2003).
  • F. B. BROWN et al., “MCNP Version 5,” Trans. Am. Nucl. Soc., 87, 273 (Nov. 2002).
  • “PWR Technology Manual,” WCAP-7730, R. J. NATH, Ed., PWR Systems Division, Westinghouse Nuclear Energy Systems (1971).
  • B. ROQUE et al., “Specification for the Phase 1 of a Depletion Calculation Benchmark Devoted to Fuel Cycles,” NEA/NSC/DOC (2004) 11 (July 2004).

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