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Technical Paper

Multilevel Methodology in Parallel Computing Environment for Evaluating BWR Safety Parameters

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Pages 267-278 | Published online: 10 Apr 2017

REFERENCES

  • M. J. THURGOOD et al., “COBRA 0TRAC-A Thermal-Hydraulics Code for Transient Analysis of Nuclear Reactor Vessels and Primary Coolant Systems,” NUREG/CR-3046, PNL-4385, Pacific Northwest National Laboratory.
  • “CORETRAN-01, Vol. 1: Theory and Numerical Analysis; Vol. 2: User’s Manual,” Electric Power Research Institute (Oct. 1992).
  • B. BANDINI, “A Three-Dimensional Transient Neutronics Routine for the TRAC-PF1 Reactor Thermal Hydraulic Computer Code,” PhD Thesis, The Pennsylvania State University (May 1990).
  • H. MOON, “A Multigroup, Multidimensional, and Nodal Diffusion and Depletion Method for the Analysis in Light Water Reactors,” PhD Thesis, The Pennsylvania State University (1989).
  • M. EDENIUS and B. FORSSEN, “CASMO-3—A Fuel Assembly Burnup Program,” STUDSVIK 0NFA-8903, Studsvik of America, Inc.
  • S. LU, “GE Simplified Boiling Water Reactor Stability Analysis in Time Domain,” PhD Thesis, The Pennsylvania State University (1997).
  • A. GEIST et al., “PVM Parallel Virtual Machine,” A User’s Guide and Tutorial for Networked Parallel Computing,” MIT Press, Cambridge, Massachusetts (1994).
  • J. BORKOWSKI and N. WADE, “TRAC-BF1/MOD1: An Advanced Best Estimate Computer Program for BWR Accident Analysis,” NUREG/CR-4356, EGG-2626, Vol. 1, Idaho National Engineering Laboratory (Aug. 1992).
  • J. SOLÍS, “Refined Multi-Level Methodology in Parallel Computing Environment for BWR RIAAnalysis,” PhD Thesis, The Pennsylvania State University (2000).
  • H. FU, “Comparative Analysis of Coupled Three-Dimensional BWR Core Transient Benchmarks,” MS Thesis, The Pennsylvania State University (2000).
  • J. SOLÍS et al., “Boiling Water Reactor Turbine Trip (TT) Benchmark,” Vol. 1: Specifications, NEA/NSC/DOC, Nuclear Energy Agency/Nuclear Science Committee (Oct. 2000).
  • C. FREPOLI et al., “COBRA-TF Simulation of BWR Bundle Dry Out Experiment,” Proc. 9th Int. Conf. Nuclear Engineering (ICONE9), Nice, France, April 8–12, 2001, p. 481 (2001).
  • C. FREPOLI et al., “Modeling of Annular Film Dry Out with COBRA-TF,” Proc. 9th Int. Conf. Nuclear Engineering (ICONE9), Nice, France, April 8–12, 2001, p. 494 (2001).
  • M. AVRAMOVA, “COBRA-TF Development, Qualification, and Application to LWR Analysis,” MS Thesis, The Pennsylvania State University (2003).
  • J. SOLÍS et al., “Development and Modeling of the Laguna Verde BWR CRDA Benchmark,” Ann. Nucl. Energy, 29, 585 (2000).

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