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1
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85162288097
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Workshop on "Simulation and Modeling for Advanced Nuclear Energy systems," DOE Offices of Nuclear Energy and Advanced Scientific Computing Research, August 15-17, 2006
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Workshop on "Simulation and Modeling for Advanced Nuclear Energy systems," DOE Offices of Nuclear Energy and Advanced Scientific Computing Research, August 15-17, 2006
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2
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85162278122
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Workshop on "Assessment of Sensitivity/Uncertainty Analysis Capabilities Applicable for the Nuclear Fuel Cycle," North Carolina State University, May, 2006
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Workshop on "Assessment of Sensitivity/Uncertainty Analysis Capabilities Applicable for the Nuclear Fuel Cycle," North Carolina State University, May, 2006
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3
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85162276930
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Workshop on "Management of Numerical Errors In Nuclear Systems Modeling," North Carolina State University, September, 2007
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Workshop on "Management of Numerical Errors In Nuclear Systems Modeling," North Carolina State University, September, 2007
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4
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85162280412
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DOE, GNEP Program Workshop on "Nuclear Energy Advanced Modeling and Simulation (NEAMS)", Argonne National Laboratory, May 2008
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DOE, GNEP Program Workshop on "Nuclear Energy Advanced Modeling and Simulation (NEAMS)", Argonne National Laboratory, May 2008
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5
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47049126146
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Efficient Subspace Methods-Based Algorithms for Performing Sensitivity, Uncertainty, and Adaptive Simulation of Large-Scale Computational Models
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Abdel-Khalik H.S., Turinsky P.J., and Jessee M.A. Efficient Subspace Methods-Based Algorithms for Performing Sensitivity, Uncertainty, and Adaptive Simulation of Large-Scale Computational Models. Nucl. Sci. Eng. 159 (2008) 256-272
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(2008)
Nucl. Sci. Eng.
, vol.159
, pp. 256-272
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Abdel-Khalik, H.S.1
Turinsky, P.J.2
Jessee, M.A.3
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8
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0001300995
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Regularization of incorrectly posed problems
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Tikhonov A.N. Regularization of incorrectly posed problems. Soviet Mathematics Doklady 4 (1963) 1624
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(1963)
Soviet Mathematics Doklady
, vol.4
, pp. 1624
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Tikhonov, A.N.1
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9
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84907101316
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Using the L-Curve for determining optimal regularization parameters
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Engl H.W., and Grever W. Using the L-Curve for determining optimal regularization parameters. Numerische Mathematik 69 (1994) 25
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(1994)
Numerische Mathematik
, vol.69
, pp. 25
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Engl, H.W.1
Grever, W.2
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10
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85162275885
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Matthew A. Jessee, Hany S. Abdel-Khalik, and Paul J. Turinsky, "Evaluation of BWR Core Attributes Uncertainties Due to Multi-Group Cross Section Uncertainties," Joint Inter. Meeting on Mathematics, Computation, and Supercomputing in Nuclear Applications, April 2007
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Matthew A. Jessee, Hany S. Abdel-Khalik, and Paul J. Turinsky, "Evaluation of BWR Core Attributes Uncertainties Due to Multi-Group Cross Section Uncertainties," Joint Inter. Meeting on Mathematics, Computation, and Supercomputing in Nuclear Applications, April 2007
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12
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85162293448
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Matthew A. Jessee, "Cross Section Adjustment Techniques for BWR Adaptive Simulation," PhD Dissertation, North Carolina State University, 2008
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Matthew A. Jessee, "Cross Section Adjustment Techniques for BWR Adaptive Simulation," PhD Dissertation, North Carolina State University, 2008
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13
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0032633612
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FORMOSA-B: A Boiling Water Reactor In-core Fuel Management Optimization Package
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Moore B.R., Turinsky P.J., and Karve A.A. FORMOSA-B: A Boiling Water Reactor In-core Fuel Management Optimization Package. Nuclear Technology 126 (1999) 153
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(1999)
Nuclear Technology
, vol.126
, pp. 153
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Moore, B.R.1
Turinsky, P.J.2
Karve, A.A.3
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14
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85162296531
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"ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6," BNL-NCS 44945, Rev. 06/05 (ENDF/B-VI), Brookhaven National Laboratory, June 2005
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"ENDF-102 Data Formats and Procedures for the Evaluated Nuclear Data File ENDF-6," BNL-NCS 44945, Rev. 06/05 (ENDF/B-VI), Brookhaven National Laboratory, June 2005
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15
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85162287440
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M.E. Dunn, "PUFF-III: A Code for Processing ENDF Uncertainty Data into Multigroup Covariance Matrices," NUREG/CR-6650, ORNL/TM-1999/235), U.S. Regulatory Commission, Oak Ridge National Laboratory, 2006
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M.E. Dunn, "PUFF-III: A Code for Processing ENDF Uncertainty Data into Multigroup Covariance Matrices," NUREG/CR-6650, ORNL/TM-1999/235), U.S. Regulatory Commission, Oak Ridge National Laboratory, 2006
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16
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85162278422
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M.D. DeHart, "TRITON: A Two Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel," ORNL/TM 2005/39, part of SCALE Version 5.1, November 2006
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M.D. DeHart, "TRITON: A Two Dimensional Depletion Sequence for Characterization of Spent Nuclear Fuel," ORNL/TM 2005/39, part of SCALE Version 5.1, November 2006
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17
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85162300984
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Argonne National Laboratory, REBUS-3/VARIANT8.0: Code System for Analysis of Fast Reactor Fuel Cycles, CCC-653, REBUS-3, Variant 8.0, 2001
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Argonne National Laboratory, REBUS-3/VARIANT8.0: Code System for Analysis of Fast Reactor Fuel Cycles, CCC-653, REBUS-3, Variant 8.0, 2001
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18
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85162282393
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ZPR-6 ASSEMBLY 7: a cylindrical assembly with mixed (Pu,U)-oxide fuel and sodium with a thick depleted-uranium reflector
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Nuclear Energy Agency
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Smith M.A., et al. ZPR-6 ASSEMBLY 7: a cylindrical assembly with mixed (Pu,U)-oxide fuel and sodium with a thick depleted-uranium reflector. Handbook of Evaluated Criticality Benchmark Experiments (2007), Nuclear Energy Agency
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(2007)
Handbook of Evaluated Criticality Benchmark Experiments
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Smith, M.A.1
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19
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85162280490
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D. Rochman et al., "Preliminary Cross Section and ν-bar Covariances for WPEC Subgroup 26," Brookhaven National Laboratory, BNL-77407-2007-IR, 2007
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D. Rochman et al., "Preliminary Cross Section and ν-bar Covariances for WPEC Subgroup 26," Brookhaven National Laboratory, BNL-77407-2007-IR, 2007
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20
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85162295126
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M. Iqbal, private communication
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M. Iqbal, private communication
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21
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85162292068
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J.R. Elkins, "Efficient Uncertainty Quantification for a Fast-Spectrum Generation IV Reactor Systems," M.Sc. Thesis, North Carolina State University, 2008
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J.R. Elkins, "Efficient Uncertainty Quantification for a Fast-Spectrum Generation IV Reactor Systems," M.Sc. Thesis, North Carolina State University, 2008
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