Nuclear Back-end and Transmutation Technology for Waste Disposal: Beyond the Fukushima Accident

Foreword......Page 6
Preface......Page 8
Cooperators......Page 10
Contents......Page 12
Part I: Basic Research for Nuclear Transmutationand Disposal: Physical and ChemicalStudies Relevant to Nuclear Transmutationand Disposal Such as Measurement orEvaluation of Nuclear Cross-Section Data......Page 17
  1.1 Introduction......Page 18
   1.2.1 Reaction via Giant Dipole Resonance......Page 19
   1.2.2 High-Energy Photons Obtained by Laser Compton Scattering......Page 20
   1.2.3 Setup of the Calculation for 137Cs......Page 22
   1.3.1 Nuclear Transmutation of 137Cs with Laser Compton Scattering......Page 23
   1.3.2 Comparison with Other Nuclides......Page 24
  1.4 Conclusion......Page 25
  References......Page 26
 Chapter 2: Recent Progress in Research and Development in Neutron Resonance Densitometry (NRD) for Quantification of Nuclear M.........Page 27
   2.2.1 The Concept of NRD......Page 28
   2.2.2 A Rough Draft of an NRD Facility......Page 29
  2.3 Development of a gamma-Ray Spectrometer for NRCA/PGA......Page 30
  2.4 Experiments for NRD Developments......Page 31
  References......Page 33
 Chapter 3: Development of Nondestructive Assay to Fuel Debris of Fukushima Daiichi NPP (1): Experimental Validation for the Ap.........Page 35
  3.2 Experiment......Page 36
  3.3 Results and Discussion......Page 38
  3.4 Summary......Page 42
  References......Page 43
 Chapter 4: Development of Nondestructive Assay of Fuel Debris of Fukushima Daiichi NPP (2): Numerical Validation for the Appli.........Page 44
  4.2 Calculational Model and Condition......Page 45
  4.3 Numerical Results and Discussion......Page 46
  References......Page 50
 Chapter 5: Precise Measurements of Neutron Capture Cross Sections for LLFPs and MAs......Page 51
  5.2 Present Situation of Data for LLFPs and MAs......Page 52
  5.3 Measurement Activities by the Activation Method......Page 53
  5.4 Measurement Activities at J-PARC/MLF/ANNRI......Page 55
  5.5 Summary......Page 56
  References......Page 57
 Chapter 6: Development of the Method to Assay Barely Measurable Elements in Spent Nuclear Fuel and Application to BWR 9x9 Fuel......Page 59
  6.1 Introduction......Page 60
  6.2 Analytical Procedure......Page 61
  6.4 Conclusion......Page 67
  References......Page 68
Part II: Development of ADS Technologies: Current Status of Accelerator-Driven System Development......Page 69
 Chapter 7: Contribution of the European Commission to a European Strategy for HLW Management Through Partitioning and Transmut.........Page 70
  7.1 Introduction......Page 71
  7.2 MYRRHA: A Flexible Fast-Spectrum Irradiation Facility......Page 73
  7.3 The MYRRHA Accelerator......Page 74
  7.4 Design of the Core and Primary System......Page 75
  7.5 MYRRHA, A Research Tool in Support of the European Roadmap for PandT......Page 78
  7.6 Conclusions......Page 81
  References......Page 82
 Chapter 8: Design of J-PARC Transmutation Experimental Facility......Page 83
   8.2.1 Outline of TEF-T......Page 84
   8.2.2 Outline of TEF-P......Page 85
  8.3 Design of Spallation Target for TEF-T......Page 86
  8.4 Conclusion......Page 88
  References......Page 89
  9.1 Introduction......Page 90
   9.2.1 Uranium-Loaded ADS Experiments......Page 91
   9.2.2 Thorium-Loaded ADS Benchmarks......Page 93
    9.3.1.1 Static Experiments......Page 94
    9.3.1.2 Kinetic Experiments......Page 95
    9.3.2.1 Static Experiments......Page 96
    9.3.2.2 Kinetic Experiments......Page 97
  References......Page 99
Part III: Mechanical and Material Technologiesfor ADS: Development of MechanicalEngineering or Material Engineering-Related Technologies for ADS and OtherAdvanced Reactor Systems......Page 101
  10.1 Introduction......Page 102
    10.2.1.1 Ultraviolet......Page 103
   10.2.2 Contact Angle Measurement......Page 104
   10.3.1 Experimental Setup and Procedure......Page 105
   10.3.2 Results and Discussion......Page 107
  References......Page 111
 Chapter 11: Experimental Study of Flow Structure and Turbulent Characteristics in Lead-Bismuth Two-Phase Flow......Page 113
   11.2.1 Four-Sensor Probe......Page 114
   11.2.2 Electromagnetic Probe......Page 115
   11.4.1 Radial Profiles of Two-Phase Flow Properties......Page 116
   11.4.2 Comparison of Interfacial Area Concentration......Page 118
   11.4.3 Bubble-Induced Turbulence......Page 119
  11.5 Conclusions......Page 120
  References......Page 121
Part IV: Basic Research on Reactor Physics of ADS: Basic Theoretical Studies for Reactor Physics in ADS......Page 122
  12.1 Introduction......Page 123
  12.2 Theory of Feynman-α Method in ADS......Page 125
  12.3 Theory of Power Spectral Density in ADS......Page 129
  12.4 Conclusions......Page 131
  References......Page 132
  13.1 Introduction......Page 133
  13.3 Analysis and Discussion of Neutron Flux......Page 134
   13.3.2 Neutron Spectrum......Page 135
  13.4 Conclusions......Page 140
  References......Page 141
Part V: Next-Generation Reactor Systems:Development of New Reactor Conceptsof LWR or FBR for the Next-GenerationNuclear Fuel Cycle......Page 142
  14.1 Introduction......Page 143
   14.2.1 Overview......Page 144
   14.2.2 Core Calculation Method......Page 146
   14.2.3 RBWR-AC......Page 147
   14.2.4 RBWR-TB......Page 150
   14.2.5 RBWR-TB2......Page 153
  14.3 Conclusion......Page 155
  References......Page 156
 Chapter 15: Development of Uranium-Free TRU Metallic Fuel Fast Reactor Core......Page 157
  15.1 Introduction......Page 158
  15.2 Issues and Measures Against the Uranium-Free TRU Metallic Fast Reactor Core......Page 159
   15.3.1 Parametric Analysis Methodology......Page 161
   15.3.2 Analysis Results for Doppler Feedback Enhancement......Page 162
   15.3.3 Analysis Results for Burnup Reactivity Swing Reduction......Page 163
   15.4.1 Specification Selected for Uranium-Free TRU Metallic Core......Page 165
   15.4.2 Performance of the Uranium-Free TRU Metallic Core......Page 166
  15.5 Conclusions......Page 168
  References......Page 169
  16.1 Introduction......Page 170
  16.2 Design of MA-Hydride Target......Page 171
  16.3 Design of Core with MA-Hydride Target......Page 172
  16.4 Transmutation Calculation......Page 173
  16.5 Discussion......Page 176
  References......Page 178
  17.1 Introduction......Page 180
  17.2 MA Transmutation Core Concept......Page 182
  17.3 MA Transmutation Rate......Page 185
   17.4.1 Sensitivity to Infinite-Dilution Cross Section......Page 188
   17.4.2 Burn-up Sensitivity......Page 190
   17.4.3 Dependence of Sensitivities on Numbers of Energy Groups......Page 191
  17.5 Reduction of Prediction Uncertainty......Page 193
  References......Page 196
 Chapter 18: Overview of European Experience with Thorium Fuels......Page 198
  18.1 Introduction......Page 199
  18.2 Thorium European Research Programme History......Page 200
  18.3 Th-MOX Fuels Irradiated in LWR Conditions......Page 201
  18.4 The Molten Salt Reactor......Page 203
  References......Page 204
Part VI: Reactor Physics Studies for Post-Fukushima Accident Nuclear Energy:Studies from the Reactor Physics Aspect forBack-End Issues Such as Treatment ofDebris from the Fukushima Accident......Page 206
  19.1 Introduction......Page 207
   19.2.1 Neutronics Calculation......Page 208
   19.2.3 Transmutation Half-Life......Page 209
   19.3.1 Reference ADS (MA-ADS)......Page 210
   19.3.2 Assumption of Pu Feed......Page 211
   19.3.3 Result of One-Batch Core......Page 212
   19.3.4 Result of six-Batch Core......Page 213
   19.4.1 Result of LWR-OT......Page 217
   19.4.2 Result of LWR-PuT......Page 218
   19.4.4 Result of ADS......Page 221
   19.4.6 Impact on the Repository......Page 224
   19.4.7 Discussion......Page 227
  19.5 Conclusion......Page 229
  Nomenclature......Page 230
  References......Page 231
  20.1 Introduction......Page 232
  20.2 Method of Calculating Sensitivity Coefficients......Page 233
   20.3.1 Analyses Conditions......Page 234
   20.3.2 Target Nuclides of Sensitivity Analyses......Page 237
   20.3.3 Results of Sensitivity Analyses......Page 240
   20.3.4 Sensitivity Analysis Using the Initial Composition Based on Measured Data......Page 245
  20.4 Conclusion......Page 247
  References......Page 248
  21.1 Introduction......Page 249
  21.2 Present Condition of 1FNPS Fuel Debris......Page 250
  21.3 Criticality Characteristics of Fuel Debris......Page 252
   21.4.1 Prevention of Criticality by Poison or Dry Process......Page 253
   21.4.2 Prevention of Criticality by Monitoring......Page 254
   21.4.4 Risk Assessment......Page 256
  References......Page 257
  22.1 Introduction......Page 258
   22.2.1 Modification of STACY......Page 259
   22.2.2 Critical Experiments on Criticality Safety for Fuel Debris......Page 261
   22.2.3 Manufacturing and Analytical Equipment for Simulated Fuel Debris Samples [12]......Page 262
  22.3 License Application and Schedule of the STACY Modification......Page 263
  22.4 Concluding Summary......Page 264
  References......Page 265
Part VII: Nuclear Fuel Cycle Policy andTechnologies: National Policy, CurrentStatus, Future Prospects and PublicAcceptance of the Nuclear Fuel CycleIncluding Geological Disposal......Page 266
 Chapter 23: Expectation for Nuclear Transmutation......Page 267
  23.2 Global Warming Is Becoming a More Serious Problem......Page 268
  23.3 The Development of Renewable Energy Must Be Promoted. However, It Will Require Sufficient Resources of Time and Budget......Page 270
   23.5.1 Safety Technology of Nuclear Energy Must Be Developed for the Future......Page 272
   23.5.3 Research and Development of Innovative Technologies, Such as Accelerator-Driven Systems, Must Be Promoted to Encourage .........Page 273
  23.6 Conclusion......Page 274
  24.1 Concerns on HLW......Page 275
  24.3 HLW Disposal Program in Japan......Page 276
  24.5 Difficulty in Site Selection......Page 279
  24.6 Six Proposals by the Science Council of Japan......Page 280
  24.7 Setting a Moratorium Period by ``Temporal Safe Storage´´......Page 281
  24.9 Awareness of the Limits of Scientific and Technical Abilities......Page 282
  References......Page 283
   25.1.1 The Situation Now......Page 284
   25.1.2 Why has Such a Situation Occurred?......Page 285
   25.1.3 Deciding the Topic......Page 286
  25.2 Research Method......Page 287
   25.2.1 Outline of the Courses......Page 288
  25.3 Reflections on the Courses......Page 289
  25.4 Results of the Questionnaire Survey......Page 290
  25.5 Issues for the Future......Page 291
  25.6 Notes......Page 292
  References......Page 293
Part VIII: Environmental Radioactivity: Development of Radioactivity Measurement Methods and Activity of Radionuclides in the .........Page 295
  26.1 Introduction......Page 296
  26.2 Partitioning of 14C into Solid, Liquid, and Gas Phases......Page 297
  26.3 Involvement of Microorganisms in the 14C Behavior......Page 298
  26.4 Transfer of 14C from Soil to Rice Plants......Page 299
  26.5 Behavior of 14C in Rice Paddy Fields......Page 301
  References......Page 302
 Chapter 27: Development of a Rapid Analytical Method for 129I in the Contaminated Water and Tree Samples at the Fukushima Daii.........Page 303
  27.1 Introduction......Page 304
   27.2.2 Separation Using Anion-SR......Page 305
  27.3 Combustion Method......Page 306
   27.4.1 Separation Using Anion-SR......Page 307
   27.4.2 Combustion Method......Page 308
  References......Page 309
Part IX: Treatment of Radioactive Waste: Reduction of the Radioactivity or Volume of Nuclear Wastes......Page 310
 Chapter 28: Consideration of Treatment and Disposal of Secondary Wastes Generated from Treatment of Contaminated Water......Page 311
  28.2 Requirements for an Inventory List and Online Waste Management System......Page 312
  28.3 Development Strategy of Waste Treatment, Storage, Transport, and Disposal Technologies......Page 313
  28.4 Formation of an RandD Implementation and Evaluation Team......Page 315
  28.6 Conclusion......Page 317
  References......Page 318
 Chapter 29: Volume Reduction of Municipal Solid Wastes Contaminated with Radioactive Cesium by Ferrocyanide Coprecipitation Te.........Page 319
  29.1 Background and Objectives......Page 320
  29.2 Principle of Ferrocyanide Coprecipitation for Cs Removal......Page 323
  29.3 Experimental......Page 324
  29.4 Results and Discussion......Page 327
  29.5 Conclusion......Page 330
  References......Page 331