Thorium Energy for the World (eBook)

Editors : Jean-Pierre Revol, et al., International Thorium Energy Committee (iThEC), Rue François Dussaud 17, 1227 Genève Acacias, Switzerland

Foreword 6
Acknowledgments 7
International Scientic Advisory Committee Members 9
Local Organizing Committee Members 10
Perspective Politique 11
Political Perspective (English Translation) 12
Conference Photos 13
List of Participants 18
ThEC13 Programme 24
Contents 28
Contributors 34
Part IInvited Speakers: Opening Talks 46
1 Welcome 47
2 Un Plaidoyer Pour L’innovation 48
Abstract 48
3 A Plea for Innovation (English Version) 50
Abstract 50
4 A Future for Thorium Power? 52
Abstract 52
Introduction 52
Today’s Nuclear Energy 53
New, Virtually Unlimited Forms of Nuclear Energy 53
How Much Thorium Is Available? 54
Many Different Sources of Thorium 54
Conclusion on the Use of Thorium 54
Thorium Breeders 55
Comparison of Uranium and Thorium Breeders 55
Early Attempts: Blending a U-235 Reactor with Thorium 55
A Purely Thermal Thorium Breeder? 55
Conclusion for Purely Thermal Thorium Operation 57
The Thorium-Driven Fast-Neutron Energy Amplifier 57
Comparing Alternatives 58
Typical Operation of the Energy Amplifier 58
General Considerations on Thorium-Driven Fission Systems 59
Basic Features of the Breeding Process 59
The Emergence of a Breeding Equilibrium 60
Magic Equilibrium for Breeding 60
Plutonium Elimination and Fissile Uranium Build-Up 60
Short Duration of Nuclear Waste and Fuel Reprocessing 60
Conclusion on Thorium Breeders 61
Proliferation Issues 62
General Considerations About the Choice of Coolant 63
Comparing Pb, Pb/Bi Eutectic and Na Coolants 63
Corrosion Studies 63
Conclusion on the Choice of Coolant 64
Working in the Neutron Capture Resonance Region 64
Accelerator-Driven Pure Thorium System Without On-Line Reprocessing 65
Some Considerations for the Optimal Arrangement 65
New Reprocessing Methods 66
A New, Simple Dry Reprocessing Method for Uranium and Plutonium Seeds 66
Long Lasting Toxicities for the Simple Fluorination Method 67
Removing the Tl-208 Radioactivity to Make New MOX Fuel 67
New Fuel Batches: A Tentative Example 67
Conclusion on Thorium Fuel Reprocessing 68
My Own Recommendations 68
References 68
Part IIInvited Speakers: National and International Thorium Programmes 69
5 Towards Sustainable, Secure, and Safe Energy Future: Leveraging Opportunities with Thorium 70
Abstract 70
Introduction 70
Sustainable Development of the Energy Sector 71
Thorium as a Solution: The Advanced Heavy Water Reactor 72
Thermo-Mechanical and Neutronic Properties of Thorium 72
The Advanced Heavy Water Reactor (AHWR) 73
Thorium as a Solution to Other Issues 74
Utilization of Uranium Resources 74
Long-Lived Waste 75
Proliferation Resistance of Th Fuels 76
Importance of Recycling and the Role of Fast Breeder Reactors, ADS, MSR 76
Conclusion 76
References 77
6 Thorium Energy and Molten Salt Reactor R& D in China
Abstract 78
Energy Demand and Environmental Challenges 78
Th–U Fuel Cycle and Molten Salt Reactors 78
Thorium-Based Molten Salt Reactor Nuclear Energy Systems 79
Research Activities 80
Conceptual Design of TMSR Experimental Reactors 81
Fuel Reprocessing Technologies 81
Structural Materials 82
TMSR Hybrid Energy System 84
Summary and Outlook 84
Acknowledgments 84
References 84
7 The Japanese Thorium Program 86
Abstract 86
Introduction 86
Research on Thorium Utilization in Japan 87
Activities for Molten Salt Applications 87
Activities for Solid Thorium Fuel Applications 87
Application of ADS to Thorium Breeding 87
National Review of Partitioning and Transmutation Technologies 88
Summary 90
References 90
8 Thorium Fuel Cycle Activities in IAEA 91
9 Overview of European Experience with Thorium Fuels 92
Abstract 92
Introduction 92
European Thorium Research Program History 93
Th--MOX Fuels Irradiated Under LWR Conditions 94
The Molten Salt Reactor 95
Conclusion 95
References 96
10 Overview of the Thorium Programme in India 97
Abstract 97
Introduction 97
Advantages of Thorium 97
Challenges of the Thorium Fuel Cycle 98
Thorium Utilisation in India [3] 99
Thorium Irradiation in Research Reactors 99
Thorium in Power Reactors 100
Flux Flattening in Pressurised Heavy Water Reactors (PHWR) Using Thorium 100
Post-irradiation Examination of the Thoria Bundles 100
Fabrication of Thorium Fuel 100
Reprocessing of Thorium Fuel 101
Waste Management in the Thoria Fuel Cycle 101
Thorium-Based Innovative Reactors 101
Advanced Heavy Water Reactor (AHWR) 101
Indian High Temperature Reactors 102
Indian Molten Salt Breeder Reactor (IMSBR) 105
Developmental Issues for Molten Salt Breeder Reactors 105
Conclusion 106
References 106
11 The Role of Thorium in Nuclear R& D in the UK
Abstract 108
UK Nuclear R& D Strategy
History of Nuclear R& D Need in the UK
Roadmap for Nuclear R& D in the UK
The Role of Fuel Cycle Modelling and the Role of Thorium 109
Fuel Cycle Modelling with ORION 109
ORION Scenarios 109
Roadmap Findings 110
Modelling of a Fast Spectrum Thorium-Fuelled Molten Salt Reactor (MSR) 110
Conclusion 112
References 112
12 Feasibility and Desirability of Employing the Thorium Fuel Cycle for Power Generation 113
Abstract 113
Introduction 113
Front End of the Thorium Fuel Cycle 114
Experience with Water Reactors 114
Experience with Other Reactors 115
Back End of the Thorium Fuel Cycle 115
Introduction 115
Experience Base in the USA in the 1960s 116
Reprocessing of Irradiated Thorium Fuel 116
Refabrication of ThO2–233UO2 Fuel 116
Irradiation Experiences with Thorium-Based Fuels 117
First-of-a-Kind and Licensability Issues for the Thorium Fuel Cycle 118
Front-End Issues of the Thorium Fuel Cycle 118
Light Water Reactors with Uranium 118
Light Water Reactors with Plutonium 120
Heavy Water Reactors 120
Back-End Issues of the Thorium Fuel Cycle 120
Feasibility and Desirability of Employing the Thorium Fuel Cycle for Nuclear Power Generation 121
Feasibility 121
Desirability 121
Past Situation 121
Current Situation 122
References 122
13 MYRRHA: A Flexible and Fast-Spectrum Irradiation Facility 124
Abstract 124
Introduction 124
The MYRRHA ADS 125
The MYRRHA Accelerator 125
The Core and Primary System 125
Irradiation Performance of MYRRHA 127
Material Irradiation Performance in the IPS 127
Irradiation Conditions Below the Beam Window 127
Use of MYRRHA for the Development of Fusion Materials 129
Conclusion 130
References 130
Part IIIInvited Speakers: Innovative Thorium-Reactor Concepts 132
14 The Thorium Fuel Cycle: Past Achievements and Future Prospects 133
Abstract 133
Reasons for Considering Thorium as a Fuel for Nuclear Reactors 133
Historical Perspective 133
The Place of the Thorium Cycle with Regard to the Uranium Cycle 134
Uranium-233 (U-233) 134
Physical Properties of Thorium 135
Natural Abundance and Reserves of Thorium 135
Past Developments of the Thorium Cycle 135
Feedback Experience of Thorium Utilization in Nuclear Reactors 135
Analysis of Incentives and Hindrances in the Historical Development of the Thorium Cycle 136
Present Status of Thorium Fuel Cycle Developments 137
Technical Characteristics and Industrial Challenges of the Thorium Fuel Cycle 137
The Front End of the Fuel Cycle 137
Mining, Milling, and Thorium Concentration 137
Thorium-Based Fuel Fabrication 138
Characteristics and Behavior of Thorium-Based Fuels in Nuclear Reactors 138
General Neutronic Characteristics 138
Fuel Behavior Under Irradiation 139
Nuclear Material Management from Thorium Fuel 139
The Back End of the Fuel Cycle 140
Fuel Reprocessing 140
U-233 Recycling 141
Final Disposal of Radioactive Waste 141
Non-proliferation Issues Regarding the Development of a Thorium Fuel Cycle 142
Conclusion 143
References 144
15 Thorium Molten Salts: Theory and Practice 145
Abstract 145
Introduction 145
The Materials of Interest 146
Thermodynamic Properties 147
Transport Properties 148
Conclusion 149
References 149
16 Liquid-Fluoride Thorium Reactor Development Strategy 151
Abstract 151
17 An Industrial View on Thorium: Possibilities, Challenges and Paths Forward 156
Abstract 156
Possibilities for Thorium Use in Nuclear Energy Systems 156
Challenges Ahead 157
Paths Forward: Thorium Can Have a Place in a Growing Nuclear Energy Future 157
18 A Global and a Turkish Perspective of Thorium Fuel for Nuclear Energy 159
Natural Properties of Thorium (Th) (Earth’s Forgotten Treasure) 159
Thorium Basics (New Green Nuke Nuclear Renaissance) 159
Why Thorium? (New Era of Safe, Clean, and Affordable Energy) 159
Uranium (Today’s Problematic Nuclear Fuel) 159
Thorium-Containing Rare-Earth Elements (REEs) 160
Monazite (REE-Th)PO4 160
Bastnasite (REE-Th)FCO3 161
Reserve Development Studies, Operation and Production Plans of Eski?ehir-Sivrihisar-K?z?lcaören Light REE + Th Field by Eti Mines 161
Monazite Cracking/Opening with Hot Concentrated H2SO4 163
Conclusion 164
References 164
19 Opportunities and Challenges for Thorium in Commercial Molten Salt Reactors 165
Abstract 165
Introduction 165
What Is ‘Commercial’? 165
The Advantages of Thorium 166
The Advantages of Molten Salt Reactors 166
Projects Considered 166
Technical Concerns 167
Comparison with Alternative Generation IV Projects 167
Materials 167
Safety 167
Drain Tank/Freeze Plug System 167
Temperature Coefficient of Reactivity of Fuel Salt 168
Reprocessing 168
Proliferation 168
Commercial Considerations 168
Conclusion 169
References 169
20 Current Czech R& D in Thorium Molten Salt Reactor (MSR) Technology and Future Directions
Abstract 170
Introduction 170
Main Results of Existing R& D Projects
Conclusions and Future Directions 174
Acknowledgments 175
References 175
21 ThEC13 Welcome Talk 176
Abstract 176
Reference 177
22 Thorium Nuclear Power and Non-proliferation 178
How Did it Work Out? 180
23 The Road to Enablement for a Liquid-Fuel Reactor Fuelled by Thorium 182
Abstract 182
Part IVInvited Speakers: Thorium-Fuel Cycle and Transmutation 183
24 Overview of the Thor Energy Thorium Fuel Development Program 184
Introduction 184
Company Background 184
Program Financing 184
The Seven-Thirty Program 185
ThADD (Thorium Additive) Fuel 185
ThMOX (Thorium Mixed Oxide) Fuel 185
The Halden Verification Program 186
Outlook 187
Acknowledgments 188
25 Utilization Potential of Thorium in Fusion–Fission (Hybrid) Reactors and Accelerator-Driven Systems 189
Abstract 189
Introduction 189
Minor Actinide Burning in Fusion–Fission (Hybrid) Reactors 190
Thorium in Fusion–Fission (Hybrid) Reactors 191
Thorium in Accelerator-Driven Systems 192
Conclusion and Recommendations 192
References 193
26 A View on the Thorium Fuel Cycle 194
Abstract 194
Background 194
Pros and Cons 194
Prospects 196
27 Recycling Challenges of Thorium-Based Fuels 198
Abstract 198
Introduction 198
Processing of Irradiated Thoria Pellets 199
Reprocessing of Irradiated Thoria Bundles from Research Reactors 199
Reprocessing of Irradiated Thoria Bundles from Power Reactors 199
Management of High Level Liquid Wastes from the Reprocessing of Thoria Based Fuels 202
28 Reprocessing of Thorium Fuel: Pyrochemical and Aqueous Routes 203
Abstract 203
Introduction 203
Pyro-Reprocessing for the MSFR Concept 204
Step-by-Step Reprocessing 206
On-Line Reprocessing 206
Off-Line Reprocessing 206
Step 1: Fluorination 206
Step 2: Reductive Extractions (2a and 2b) 207
Step 3: Back-Extraction of Lanthanides 207
Step 2c: Back-Extraction of Actinides 207
Step 4: Introduction of 233U and Redox Control of the Fuel Salt 207
Step 5: Recovery of Salt and Metallic Phase Composition 208
The Behavior of the Elements During Reprocessing 208
Aqueous Reprocessing of Solid Thorium Oxide Fuel [13, 14] 208
Solid Fuel Dissolution 208
Liquid–Liquid Extraction 208
Conclusion 208
References 209
29 Paul Scherrer Institute’s Studies on Advanced Molten Salt Reactor Fuel Cycle Options 210
Abstract 210
Introduction 210
Appealing MSR Features 210
Excellent Neutron Economy 210
No Need for Fabrication 212
Flexibility of the Fuel Cycle 213
Inherent Safety 213
Direction of Own MSR Research: Reduction of Challenges 214
Reduction of Structural Material Irradiation Embrittlement 214
Simplification of the Reprocessing Strategy in the Th–U Cycle 214
Conclusion 216
References 217
Part VInvited Speakers: Thorium-Reactor Physics 218
30 Nuclear Data Development Related to the Th–U Fuel Cycle in China 219
Abstract 219
Introduction 219
Measurement of nFPYs for 232Th 219
Evaluation of nFPYs for 232Th 219
Re-evaluation of Nuclear Reaction Data for 233U and 232Th 220
Nuclear Data Validation for 233U and 232Th 221
Summary 221
References 221
31 Nuclear Data Development Related to the Th–U Fuel Cycle in India 223
Abstract 223
Introduction 223
Thorium Utilization Studies Need New and Improved Nuclear Data 223
Initial Indian Efforts at Kalpakkam on Nuclear Data for the Thorium Fuel Cycle 225
Nuclear Data Physics Experiments for the Thorium Fuel Cycle 225
Mirror Websites for Nuclear Data 226
Indian EXFOR Compilations of Nuclear Data 226
IAEA Coordinated Research Projects (CRPs) 227
Analyses of Irradiation of Thorium Bundles in PHWRs 227
Positive Temperature Coefficient of the Reflector in KAMINI 228
Formation of the Nuclear Data Physics Centre of India (NDPCI) 228
Concluding Remarks 229
Acknowledgments 229
References 229
32 Nuclear Data for the Thorium Fuel Cycle and the Transmutation of Nuclear Waste 231
Abstract 231
Introduction 232
The Neutron Time-of-Flight Facility (n_TOF) at CERN 233
Contributions from the n_TOF Facility to Nuclear Data 234
Nuclear Data Measurements During Phase-I 234
Nuclear Data Measurements During Phase-II 235
Conclusion and Outlook 236
References 237
33 Fast Reactor Physics 239
Abstract 239
Introduction 239
Calculation Tools, Assumptions, and Models 240
Results for EQL-U and EQL-Th Closed Fuel Cycles in SFR 241
Reaction Rates 241
Fuel Composition 242
Neutron Balance 243
Safety Parameters 243
Radiotoxicity and Decay Heat 244
Summary 244
Acknowledgments 245
References 245
34 Introduction to the Physics of Thorium Molten Salt Fast Reactor (MSFR) Concepts 246
Abstract 246
Introduction 246
Description of the MSFR Concept 247
Core and System Designs 247
Salt Cleaning and Reprocessing 248
MSFR Fuel Cycle Scenarios 250
Safety Issues 250
Safety Approach and Risk Analysis for a Liquid-Fueled Reactor 251
Decay Heat Removal 251
Issues and Demonstration Steps of the Concept Viability 252
Conclusion 253
Acknowledgments 253
References 253
Part VIInvited Speakers: Accelerator-Driven Systems 255
35 Accelerator-Driven Systems (ADS) Physics and Motivations 256
Abstract 256
A Brief History of ADS 256
Basic Elements of ADS 258
Subcritical Core Physics 258
Accelerators for ADS 260
Accelerator Requirements 260
ADS Proposals 262
Summary of Recent ADS Developments 262
Conclusion 262
References 262
36 Review of Accelerators for Accelerator-Driven Systems (ADS) 264
Abstract 264
Introduction 264
ADS Accelerator Specifications 264
Basic ADS Characteristic 264
Basic Accelerator Considerations 265
Energy 265
Beam Intensity 266
Reliability 266
The OECD-NEA (Nuclear Energy Agency) Assessment 266
Linear Accelerators and Cyclotrons for ADS 266
Cyclotrons 266
Linear Accelerators 267
Reliability Implementation 268
Present and Future High-Power Accelerator Projects 268
Concluding Remarks 268
References 269
37 Cyclotron Drivers for Accelerator-Driven Systems 270
Introduction 270
The PSI H+ Two-Stage Cyclotron 270
The TRIUMF H– Single-Stage Cyclotron 270
Beam Dynamic Issues 271
Single-Turn Extraction 271
Stripping or Overlapping-Turns Extraction 272
Two Examples of High-Power Cyclotron Designs 272
The Energy Amplifier Project 272
The TRADE Project 273
New Advanced High-Power Cyclotron Designs 275
The 800 MeV Superconducting Strong Focusing Cyclotron 275
The DAE?ALUS Project 275
The AIMA DEVELOPPEMENT (AD) Single-Stage High-Power Cyclotron 275
Critical Issues for an Industrial ADS Cyclotron Driver 276
Ion Sources 276
RF Problems 277
Extraction Elements 277
Vacuum Problems 277
High Global Yield of the Accelerator 277
A Cluster of Cyclotron-Based ADS for an Industrial Power Plant 277
Conclusion 278
Acknowledgments 278
References 278
38 Euratom MAX Project: The MYRRHA Accelerator eXperiment R& D Program
Abstract 280
Introduction 280
Overview of the MYRRHA Accelerator 281
Tolerance to Faults 281
Injector Beam Reconfiguration in Fault Cases 281
Superconducting Linac Beam Reconfiguration in Fault Cases 283
Main Design Aspects 283
Fault Compensation Scheme 283
Conclusion 284
Acknowledgments 285
References 285
39 Accelerators for Accelerator-Driven Subcritical Reactors 286
Abstract 286
Accelerator Requirements 286
Beam Energy 286
Limits to Reactivity: The Protactinium Problem 286
Beam Current and Machine Power 287
Reliability 287
The DAE?ALUS MultiMegawatt Cyclotron 288
The Main Cyclotron 288
The Non-scaling Fixed-Field Alternating Gradient (nsFFAG) 289
The FFAG, Past and Present 289
The nsFFAG 289
An NsFFAG for ADSR 290
Conclusion 292
References 292
40 Spallation Target Developments 293
Abstract 293
Introduction 293
Spallation Target Development Roadmap 293
Spallation Target Development at SINQ 294
Spallation Target Development at SNS 296
Spallation Target Collaboration with J-PARC 297
Conclusion 297
Acknowledgments 297
References 297
41 MEGAPIE: The World’s First High-Power Liquid Metal Spallation Neutron Source 298
Abstract 298
Introduction 299
Description of the Target 299
The Road to Irradiation of the Target 300
Decommissioning Phase 301
Post-irradiation Examinations 302
Conclusion 305
Acknowledgments 305
References 305
42 Target Design for a Thorium Accelerator-Driven Molten Salt Reactor (AD-MSR) 307
Abstract 307
Introduction 307
The MSR Roadmap 307
1st Stage 307
2nd Stage 308
3rd Stage 308
4th Stage 308
5th Stage 308
The Accelerator-Driven Molten Salt Reactor Concept 308
Characteristics of the Neutron Spallation Source 309
FLUKA Model 309
FLUKA Results 309
Neutron Fluence, Power, and Fission Density 309
Nuclear Reactions 310
Neutron Energy Distribution 310
Discussion and Conclusions 310
Acknowledgments 312
References 312
43 Virginia Nuclear Energy Frontier Research Center 314
Abstract 314
44 Thorium-Loaded Accelerator-Driven System Experiments at the Kyoto University Research Reactor Institute 316
Abstract 316
Introduction 316
Experimental Settings 317
Thorium Fission Reaction 317
Thorium Plate Irradiation 317
Thorium-Loaded ADS Benchmarks 317
Results and Discussion 318
Thorium Fission Reactions 318
Thorium Plate Irradiation 319
Thorium-Loaded ADS Benchmarks 319
Static Experiments 319
Kinetic Experiments 320
Conclusion 320
Acknowledgments 320
References 320
45 A Status and Prospect of Thorium-Based ADS in Korea 322
Abstract 322
Introduction 322
Past ADS Development in Korea: ADS Research in KAERI 322
Present ADS Status in Korea: ADS Research in Universities 323
TNudy (ROOT Nuclear Data Library) 323
Partitioning and Radiochemistry of Thorium 324
Transmutation of LLFPs 325
Life Cycle Assessment for ADS 325
ADS Cyclotron Design at Sungkyunkwan University 325
Summary 327
References 327
46 Proposal of the ADS Research Stand Based on the Linac of the Institute for Nuclear Research of the Russian Academy of Sciences 328
Abstract 328
Introduction 328
Infrastructure Specifics of the INR Linac and Neutron Complex 329
Linear Accelerator (Linac) 329
Some Characteristics of the Experimental Complex 329
Neutron Source Complex 329
Installation Capacity and Basic Requirements 332
Main Goals, Objectives, and Technical Requirements of the ADS Stand [3–5] 332
Stand Conceptual Layout [3–5] 333
Target 333
PbBi Inserts 333
Some Technical Aspects on Safety 334
Some Characteristics of the Blanket 334
Physical Aspects of Safety 336
Control System and Compensation Reactivity Effects 336
Fuel Rods 336
Some Design Characteristics of the Installation 337
Horizontal Beam Input 337
Target Module 339
PbBi Module Positions 339
Simulation of Neutron Physical Characteristics [5] 339
1st Stage 339
2nd Stage 339
Main Results and Conclusions [5] 340
Target Optimization 340
Energy Output 340
Reactivity Effects 340
Importance of the Neutron Source 341
PbBi versus D2O 341
Directions of Further Research 342
Acknowledgments 342
References 343
47 A New Concept for ADS Spallation Target: Gravity-Driven Dense Granular Flow Targets 344
Abstract 344
Introduction 344
Challenges of ADS High-Power Targets and the New Concept 345
Discussion and Conclusion 347
Acknowledgments 348
References 348
48 Accelerator-Driven Systems for Thorium Utilization in India 349
Abstract 349
Introduction 349
Overview of the Program for ADS Development 349
Accelerator Development 349
Target Development 350
Reactor Physics Studies and Developments 351
Computer Codes and Nuclear Data 351
Experimental Program: The Purnima Subcritical Facility 351
Theoretical Studies Related to the Experimental Program 351
Thorium Utilization in Accelerator-Driven Systems 352
The Power-Producing Breeder ADS 353
In Situ Breeding and Burning in Once-Through Cycles: The Thorium Burner 353
Heavy Water Moderated Thorium Burning ADS 353
Thorium Burning Fast ADS 353
Accelerator Production of 233U for Use in Critical Reactors 354
Thorium Utilization in Molten Salt Reactors 354
Conclusion 355
References 355
49 iThEC’s Approach Toward Nuclear Waste Transmutation and Energy Production with Thorium 357
Abstract 357
Introduction 357
A Path to Sustainability the Thorium-ADS
Advantages of an ADS 359
Transmutation of Plutonium with Thorium 360
The Way Forward Proposed by iThEC 360
Conclusion 361
References 361
Part VIISummary of the Round Table Discussion 362
50 National and International Thorium Programmes (Sessions 1, 2) 363
National and International Programmes 363
51 Innovative Thorium Reactor Concepts (Sessions 3, 4, 5) 364
Thorium Reactor Concepts 364
India’s Thorium Programme 364
UK Study 364
Is the Thorium Cycle Feasible? Is It Desired? 364
Alex C. Mueller’s Personal View 365
Other Important Points 365
Other Important Views on Thorium 365
52 Thorium-Fuel Cycle and Transmutation (Sessions 6, 7) 366
References 367
53 Thorium-Reactor Physics (Session 8) 368
54 Accelerator-Driven Systems: The Accelerator (Session 9) 369
ADS: The Accelerator 369
Requirements for ADS Accelerators 369
Review of the Contributions 369
Conclusion and Round Table Discussion 370
55 Accelerator-Driven Systems: The Spallation Target (Session 10) 371
ADS: The Spallation Neutron Source 371
References 372
56 Accelerator-Driven Systems: National Projects (Session 11) 373
ADS: National Projects 373
57 Accelerator-Driven Systems: National Projects (Session 12) 374
ADS: National Projects 374
References 375
Part VIIConclusion 376
58 ThEC13 Summary and a Look into the Future 377
ThEC13: A Significant Success 377
Thorium 377
Options for the Practical Utilization of Thorium 377
National and International Thorium Programs 379
Thorium Fuel Cycle 380
Simulation of Thorium Systems 380
Conclusion 380
Acknowledgments 381
References 381
Part IXPosters: National and International Thorium Programmes 382
59 Neutronic Analysis and Transmutation Performance of Th-Based Molten Salt Fuels 383
Introduction 383
Models for Reactor and Fuels 383
Results 383
Conclusion 385
References 385
60 Neutron Irradiation of Thorium-Based Fuels: Comparison Between Accelerator-Driven Systems and Fusion–Fission Systems 386
Abstract 386
Introduction 386
Methodology 386
Results 386
Conclusion 388
Acknowledgments 388
References 388
Part XPosters: Innovative Thorium-Reactor Concepts 389
61 Generation IV Reactor Cooling by “Gas-Lift” 390
Introduction 390
Description of the Experimental Device 390
Conditions for the Use of “Gas-Lift” 391
Conclusion 392
Acknowledgments 392
References 392
62 The Bumpy Road to a Technology Strategy Board Grant 393
Abstract 393
The Bumpy Road to a Technology Strategy Board Grant 393
Immediate Disappointment 394
Objectives 394
63 Experimental Activities on Heavy Liquid Metal Thermo-Hydraulics 395
Abstract 395
Introduction 395
Spallation Targets for Accelerator-Driven Systems (ADS) 395
Heat Transfer in Fuel-Element-Representative Geometries 395
Conclusion 396
References 396
64 Combined Effect of Irradiation and Molten Fluoride Salt on Ni-Based Alloys 397
Introduction 397
Materials and Electron Irradiation Test Facility (EITF) 397
Mechanical Tests 397
Microstructural and Composition Investigations 397
Corrosion Tests 398
Conclusion 398
Acknowledgments 398
References 398
Part XIPosters: Thorium-Fuel Cycle and Transmutation 399
65 High-Conversion Th-U-233 Fuel Cycle for Current Generation in PWRs 400
Abstract 400
Introduction 400
Results 400
References 401
66 Thorium and Transuranic (TRU) Advanced Fuel Cycle: An Option for Brazilian Nuclear Plants 402
Abstract 402
Introduction 402
Methodology 402
Results 402
Conclusion 404
Acknowledgements 404
Reference 404
67 Evaluation of Fuel Cycles Based on U–Th and Pu–Th Mixtures in a Very High Temperature Hybrid System 405
Abstract 405
Parameters 405
Results 405
Conclusions 406
Acknowledgments 406
References 406
68 Thermal Modeling of Thorium Sphere-Pac Fuel in an Annular Pin Design 407
Abstract 407
Introduction 407
Model, Results, and Conclusions 407
Acknowledgments 408
References 408
69 Theoretical Modelling of ThO2 Grain Boundaries Using a Novel Interatomic Potential 409
Abstract 409
Introduction 409
Methodology: Fitting a New Interatomic Potential 409
Methodology: Modelling Grain Boundaries 409
Current and Future Research 410
References 410
70 A Novel Approach for Preferential Recovery of 90Sr from Irradiated ThO2 411
Abstract 411
Part XIIPosters: Thorium Reactor Physics 413
71 Preliminary Applications of ANET Code for the Investigation of the Hybrid Soliton Reactor Concept 414
Abstract 414
The ANET Code and the Hybrid Soliton Reactor (HSR) Concept 414
Results and Concluding Remarks 414
72 The Proto-Earth Georeactor: A Thorium Reactor? 416
References 417
Part XIIIPosters: Accelerator-Driven Systems 418
73 GEM*STAR Multipurpose Applications 419
Abstract 419
Reference 421
74 A Provisional Study of ADS Within the Turkic Accelerator Complex Project 422
Abstract 422
Introduction 422
Thorium in Turkey 422
The TAC Proton Accelerator 422
Project PROMETHEUS 423
Conclusion 423
References 423
75 ADS Research Activities at Sungkyunkwan University 424
Introduction 424
Research Topics 424
Nuclear Data Library (TNudy) 424
Transmutation by Adiabatic Resonance Crossing Method 424
Radiochemistry 425
Development of Detectors 425
Life Cycle Assessment 425
Summary 425
References 426
76 Design of a Compact Transportable Neutron Source in TIARA/EU/FP7 427
Abstract 427
Retained Design 427
Specific Design Details 427
77 A 800 MeV/u, 16 MW Cyclotron Complex 431
Abstract 431
References 432
78 A 4 MW High-Power Spallation Source for an ADS Demonstrator 434
Abstract 434
Introduction 434
Main Features of the Design 434
References 436
79 Subcriticality Monitoring for the Accelerator-Driven Thorium Reactor (ADTRTM) Control 437
Acknowledgements 438
References 438
80 Utilization Potential of Thorium in CANDU Reactors and in Fusion–Fission (Hybrid) Reactors 439
Abstract 439
References 440
81 Stop Designing Reactors! 441