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Topical Report, ANP-10297NP, Revision 0, ANP-10297NP Revision 0 The ARCADIA® Reactor Analysis System for PWRs Methodology Description and Benchmarking Results Topical Report March, 2010 AREVA NP Inc. (c) 2010 AREVA NP Inc. Copyright © 2010 AREVA NP Inc. All Rights Reserved AREVA NP Inc. ANP-10297NP Revision 0 The ARCADIA® Reactor Analysis System for PWRs Methodology Description and Benchmarking Results Topical Report Page i Nature of Changes Section(s) Item or Page(s) Description and Justification AREVA NP Inc. ANP-10297NP Revision 0 The ARCADIA® Reactor Analysis System for PWRs Methodology Description and Benchmarking Results Topical Report Page ii Contents Page 1.0 Introduction ....................................................................................................................1-1 1.1 References .........................................................................................................1-2 2.0 APOLLO2-A Methodology..............................................................................................2-1 2.1 Introduction.........................................................................................................2-1 2.2 Methodology Overview.......................................................................................2-1 2.2.1 Cross-Section Preparation (Weighting Flux Computation) .....................................................................................2-2 2.2.2 Master Flux Computation...................................................................2-4 2.2.3 Depletion............................................................................................2-5 2.2.4 Branch Calculation.............................................................................2-5 2.2.5 Gamma Calculation ...........................................................................2-5 2.2.6 Miscellaneous Models .......................................................................2-6 2.3 Nuclear Data Libraries........................................................................................2-8 2.3.1 Neutron Library ..................................................................................2-8 2.3.2 Gamma Libraries ...............................................................................2-8 2.4 Self-shielding....................................................................................................2-10 2.4.1 Introduction ......................................................................................2-10 2.4.2 Overall Self-shielding Process.........................................................2-11 2.4.3 Theory..............................................................................................2-12 2.5 Solving the Boltzmann Transport Equation ......................................................2-15 2.5.1 The Boltzmann Transport Equation .................................................2-16 2.5.2 Collision Probability solver (CP) ......................................................2-19 2.5.3 Integro-Differential Transport Solver (IDT) ......................................2-21 2.5.4 MOC Solver .....................................................................................2-26 2.5.5 Generic Solution Process ................................................................2-30 2.5.6 Geometry, Boundary Condition and Symmetry ...............................2-32 2.6 Flux Reconstruction..........................................................................................2-34 2.7 Leakage Correction ..........................................................................................2-35 2.8 Fuel Depletion ..................................................................................................2-36 2.9 Gamma Calculation..........................................................................................2-37 2.10 Miscellaneous Models ......................................................................................2-37 2.10.1 Energy Deposition Model.................................................................2-37 2.10.2 Pin Detector Model ..........................................................................2-38 2.10.3 Reflector Model................................................................................2-39 2.10.4 Kinetics Data....................................................................................2-39 2.10.5 Color-Set Model...............................................................................2-40 AREVA NP Inc. ANP-10297NP Revision 0 The ARCADIA® Reactor Analysis System for PWRs Methodology Description and Benchmarking Results Topical Report Page iii 3.0 ARTEMIS Neutronic Methodology .................................................................................3-1 3.1 Introduction.........................................................................................................3-1 3.2 The Steady-state 3D Multi-group Flux Solver FLUXS........................................3-1 3.3 The 3D Multi-group Transient Flux Solver FLUXT .............................................3-8 3.4 Acceleration by Multi-level Coarse Mesh Rebalancing ....................................3-12 3.5 Cross-Section Model ........................................................................................3-12 3.6 Nuclide Depletion .............................................................................................3-14 3.7 Pin Reconstruction ...........................................................................................3-15 3.8 Coupled Neutronic, Thermal-Hydraulic, and Fuel Rod Calculations ................3-19 3.9 Fuel Assembly Shuffling and Repository..........................................................3-21 3.10 References .......................................................................................................3-22 4.0 ARTEMIS (COBRA-FLX) Thermal-Hydraulic Methodology ...........................................4-1 4.1 Introduction.........................................................................................................4-1 4.2 COBRA-FLX Description....................................................................................4-2 4.2.1 Problem Formulation .........................................................................4-2 4.2.2 Code Structure...................................................................................4-5 4.3 COBRA-FLX Coupling With ARTEMIS...............................................................4-5 4.3.1 Development of Thermal-Hydraulic Parameters That Are Used in Coupling and Their Nodal Basis ....................................4-5 4.3.2 One-way and Two-way Coupling.......................................................4-6 4.4 Safety Margin Evaluation ...................................................................................4-7 4.5 References .........................................................................................................4-7 5.0 ARTEMIS Fuel Rod Module Methodology .....................................................................5-1 5.1 Introduction.........................................................................................................5-1 5.2 Thermal Solver ...................................................................................................5-2 5.3 Physical Properties.............................................................................................5-3 6.0 APOLLO2-A Validation ..................................................................................................6-1 6.1 Introduction.........................................................................................................6-1 6.2 Critical Experiments ...........................................................................................6-1 6.2.1 Description of the Experimental Configurations.................................6-2 6.2.2 Measurement Comparisons...............................................................6-4 6.2.3 Discussion of Results – Critical Experiments ....................................6-9 6.3 Integral Experiments ..........................................................................................6-9 6.3.1 Description of the Experimental Configurations: VALDUC ..........................................................................................6-10 6.3.2 Measurement Comparisons: Reactivity ...........................................6-10 6.3.3 Discussion of Results ......................................................................6-11 6.4 Spent Fuel Analyses ........................................................................................6-11 6.4.1 Description of the Experiments........................................................6-12 6.4.2 Measurement Comparisons.............................................................6-14 AREVA NP Inc. ANP-10297NP Revision 0 The ARCADIA® Reactor Analysis System for PWRs Methodology Description and Benchmarking Results Topical Report Page iv 6.4.3 Isotopic Burnup Analysis Discussion of Results ..............................6-18 6.5 References .......................................................................................................6-19 7.0 REFLECTOR Treatment ................................................................................................7-1 7.1 Introduction.........................................................................................................7-1 7.2 Reflector Physics................................................................................................7-1
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