| | MODULAR PEBBLE-BED REACTOR PROJECT |
| | 6,33 | | MB |
| | 111 | | stron |
| | 4727 | | ID | Massachusetts Institute of Technology |
| | 2002 | | rok |
| | Table of Contents |
| | 1.0 Introduction 1 |
| | 2.0 Gas Reactor Fuel Performance Studies 2 |
| | 2.1 Studies at the INEEL 2 |
| | 2.1.1 Stress Model Development and Approach 3 |
| | 2.1.1.1 Basic Particle Behavior 3 |
| | 2.1.1.2 Material Properties 3 |
| | Creep 4 |
| | Shrinkage 4 |
| | Weibull Parameters 5 |
| | Elastic Properties 6 |
| | 2.1.1.3 Evaluation of Shrinkage Cracks in the IPyC 6 |
| | 2.1.1.4 Basic Approach Used in Fuel Performance Model 6 |
| | Structural Models 6 |
| | Statistical Evaluations 8 |
| | 2.1.1.5 Cracked Particle Model and Results for NPR Experiments 9 |
| | 2.1.1.6 Standard Particle Model and Results for EU High-Burnup Case 11 |
| | 2.1.1.7 Effects of Thermal Cycling 13 |
| | 2.1.1.8 Effects of Varying Poisson’s Ratio in Creep for the Pyrocarbons 14 |
| | 2.1.1.9 Calculating Particle Batch Failure Probabilities Using an Integral Formulation 14 |
| | 2.1.2 Fission Gas Release, CO Production and Fission Product Chemistry 15 |
| | 2.1.2.1 Fission Gas and CO Release Model 15 |
| | 2.1.2.2 Fission Product Chemistry Module 17 |
| | 2.2 Studies at MIT 20 |
| | 2.2.1 In-Core Environment: Simulation of Core Fueling 21 |
| | 2.2.2 Chemical Model 21 |
| | 2.2.3 Mechanical Model Development 21 |
| | 2.2.3.1 Benchmarking the Stress Analysis Model 21 |
| | Simulations of NPR-type and HTTR-type Fuel Particles 23 |
| | 2.2.3.2 Fuel Failure Probability 28 |
| | 2.2.4 Conclusions and Future Work 28 |
| | References for Section 2 28 |
| | 3.0 Reactor Physics Research 30 |
| | 3.1 INEEL Work 30 |
| | 3.1.1 Introduction 30 |
| | 3.1.2 Advances in the Development of PEBBED 31 |
| | 3.1.2.1 PEBBED 2.0 – the FORTRAN Version of PEBBED 31 |
| | 3.1.2.2 Expanded Isotopics Tracking 31 |
| | 3.1.2.3 Multigroup Energy Treatment 31 |
| | 3.1.2.4 Enhancements to the Geometric Modeling Capability 31 |
| | 3.1.2.5 Ex-Core Radionuclide Decay 32 |
| | 3.1.2.6 The Matrix Approach to Recirculation Analysis 32 |
| | Nuclide Flow in Recirculating Cores 32 |
| | 3.1.3 Application of PEBBED to the Analysis of Pebble-Bed Reactors 34 |
| | 3.1.3.1 Evaluation of Peak Neutron Flux and Core Eigenvalue of HTR Modul 200 and Eskom PBMR |
| | 34 |
| | 3.1.3.2 Support of Planning for Testing of Eskom PBMR Fuel in the Advanced Test Reactor 36 |
| | 3.1.4 Study of the Potential for PBRs to be Diverted for Production of Material for Nuclear |
| | Weapons 39 |
| | 3.1.4.1 Introduction 39 |
| | 3.1.4.2 Methodology 39 |
| | 3.1.4.3 Results 40 |
| | 3.1.4.4 Conclusions 40 |
| | 3.1.5 Progress at Georgia Institute of Technology on the Development of a Method to Compute |
| | Diffusion Parameters 41 |
| | 3.1.6 Analysis of Plutonium Concentration and Isotopics Based on the Reactivity-Limited Burnup of |
| | Pebble-Bed Reactor Fuel Using Various Enrichments 42 |
| | 3.1.6.1 Introduction 42 |
| | 3.1.6.2 Modeling Methods 42 |
| | 3.1.6.3 Reactivity-Limited Burnup 43 |
| | 3.1.6.4 Plutonium Isotopics 44 |
| | 3.1.6.5 Conclusions 44 |
| | 3.1.7 Summary and Outlook 45 |
| | 3.2 MIT Work 45 |
| | 3.2.1 Introduction 45 |
| | 3.2.2 Modeling Considerations 46 |
| | 3.2.3 HTR-PROTEUS 47 |
| | 3.2.4 HTR-10 49 |
| | 3.2.5 ASTRA 50 |
| | References for Section 3 53 |
| | 4.0 Reactor Safety and Thermal Hydraulics Modeling 55 |
| | 4.1 INEEL Research 55 |
| | 4.1.1 ATHENA Code Simulation 55 |
| | 4.1.1.1 ATHENA Model 55 |
| | 4.1.1.2 Results 59 |
| | 4.1.1.3 Conclusions 62 |
| | 4.1.2 Scoping Analyses 62 |
| | 4.1.3 MELCOR Modeling 62 |
| | 4.1.3.1 MELCOR Model 62 |
| | 4.1.3.2 Oxidation Model 64 |
| | 4.1.3.3 Results 65 |
| | 4.1.3.4 Conclusions 68 |
| | 4.2 MIT Research 68 |
| | 4.2.1 The Loss-of-Coolant Accident with Depressurization 68 |
| | 4.2.1.1 Introduction 68 |
| | 4.2.1.2 Description of the Model 68 |
| | 4.2.1.3 Decay Heat Generation 75 |
| | 4.2.1.4 Boundary Conditions 76 |
| | 4.2.1.5 The Calculation and the Sensitivity Analysis 77 |
| | 4.2.1.6 Conclusions and Recommendations 80 |
| | 4.2.2 The Air Ingress Accident 82 |
| | 4.2.2.1 Introduction 82 |
| | 4.2.2.2 The Physical Process of the Accident 82 |
| | 4.2.2.3 Main Reactions 83 |
| | Important Parameters Governing these Reactions 83 |
| | 4.2.2.4 The Pressure Drop 84 |
| | 4.2.2.5 The Model 84 |
| | The Main Assumptions 84 |
| | 4.2.2.6 Calculation Procedures 87 |
| | 4.2.2.7 Results 87 |
| | 4.2.2.8 Conclusions and Future Work 92 |
| | References for Section 4 93 |
| | 5.0 Conclusions 94 |
| | Fuel Performance Model Development 94 |
| | Core Neutronics 94 |
| | Safety Analysis 94 |
| | Appendix: Air Ingress Analyses on a High Temperature Gas-Cooled Reactor (paper published in |
| | Proceedings of 2001 ASME International Mechanical Engineering Congress and Exposition) 95 |