Fuel cycle options for light water reactors and heavy water reactors : proceedings of a Technical Committee meeting

COVER......Page 1
FOREWORD......Page 3
EDITORIAL NOTE......Page 4
CONTENTS......Page 5
SUMMARY......Page 7
GLOBAL AND NATIONAL PERSPECTIVES FOR DEVELOPING ADVANCED FUEL CYCLE OPTIONS (SESSION 1)......Page 13
2. NEW REALITIES......Page 14
4. PLUTONIUM MANAGEMENT (KEY ISSUE PAPER NO. 2)......Page 15
7. INTERNATIONAL COOPERATION (KEY ISSUE PAPER NO. 6)......Page 17
REFERENCES......Page 18
2. DIGEST OF KEY ISSUE PAPER #3......Page 19
3. RELATIONSHIP BETWEEN KEY ISSUES PAPER #3 AND PAPERS GIVEN IN THIS TCM......Page 24
4. RECOMMENDATIONS FOR ACTION FOLLOWING THIS TCM......Page 25
5. SOME POSSIBLE WORK PROGRAMS......Page 27
6. CONCLUSION......Page 28
2. FUEL CYCLE OPTIONS......Page 29
3. EVOLVING PRECEPTIONS AND INDIAN OPTIONS......Page 30
4. THE INDIAN NUCLEAR ENERGY PROGRAMME......Page 31
REFERENCES......Page 38
1. INTRODUCTION......Page 39
2. MANAGEMENT OF SPENT NUCLEAR FUEL......Page 40
3. PLUTONIUM UTILISATION......Page 42
4. MANAGEMENT OF REPROCESSED URANIUM AND DEPLETED URANIUM......Page 45
7. PERSPECTIVES OF THE FUTURE DEVELOPMENT OF THE NUCLEAR FUEL CYCLE......Page 46
REFERENCES......Page 47
1. INTRODUCTION......Page 48
2. LWR FUEL PERFORMANCE AT HIGH BURNUP......Page 49
3. FUEL PERFORMANCE UNDER TRANSIENT CONDITIONS......Page 51
4. PROGRAM DESCRIPTION AND PRODUCTS......Page 55
5. TEST FACILITIES......Page 57
REFERENCES......Page 59
1. INTRODUCTION......Page 62
2. CANDU FEATURES FACILITATING ADVANCED FUEL CYCLES......Page 63
3. NATURAL URANIUM FUEL IN CANDU REACTORS......Page 64
5. SEU IN CANDU REACTORS......Page 65
6. RECYCLE OF SELF-GENERATED PLUTONIUM......Page 66
7.CANDU/PWR SYNERGISM......Page 67
8. CANDU MOX FOR PLUTONIUM DISPOSITIONING......Page 69
10. THORIUM FUEL CYCLES IN CANDU REACTORS......Page 70
12. SUMMARY: CANDU FUEL-CYCLE VISION......Page 72
REFERENCES......Page 73
1. INTRODUCTION......Page 76
2. STANDARD CANDU-6 FUEL MANUFACTURING IN ROMANIA......Page 77
3. ADVANCED CANDU FUEL CYCLE- AN IMPORTANT DIRECTION OF THE ROMANIAN NUCLEAR FUEL PROGRAM......Page 83
4. CONCLUSIONS......Page 84
REFERENCES......Page 85
1. INTRODUCTION......Page 87
2. DEVELOPMENTS AROUND THE USE OF SEU FUEL......Page 89
3. PROJECT "USE OF SEU IN ATUCHA-1 NPP" (1)......Page 91
REFERENCES......Page 97
FUEL DESIGN, PERFORMANCE AND TESTING (SESSION 2)......Page 98
1. INTRODUCTION......Page 99
2. TREAT FACILITY BACKGROUND......Page 100
4. CONCEPTUAL DESIGN OF A PRESSURIZED WATER LOOP......Page 103
5. EVALUATION OF HYPOTHETICAL TREAT RIA TESTS......Page 106
6. SUMMARY......Page 108
REFERENCES......Page 109
1. INTRODUCTION......Page 110
2. METHOD......Page 111
REFERENCES......Page 117
1. INTRODUCTION......Page 118
2. TECHNOLOGIES......Page 119
3. PROPERTIES OF Nb2O5-DOPED UO2 PELLETS......Page 122
4. BENEFICIAL EFFECTS......Page 124
REFERENCES......Page 126
1. INTRODUCTION......Page 128
3. DEFINITION OF THE NUMBER AND LENGTH OF THE FUEL RODS......Page 131
5. NEUTRONIC CALCULATIONS......Page 132
6. THERMOMECHANICAL BEHAVIOR OF FUEL ROD......Page 133
REFERENCES......Page 138
2. SEU-43 BUNDLE DESIGN......Page 140
3. FUEL ELEMENT DESIGN OPTIMISATION......Page 143
4. SIGNIFICANT ASPECTS REGARDING SEU-43 FUEL ELEMENT DESIGN EVALUATION......Page 144
5. FUEL-BUNDLE OUT OF PILE TESTING......Page 148
7. CONCLUSIONS......Page 149
REFERENCES......Page 150
1. INTRODUCTION......Page 152
3. CANFLEX VERIFICATION PROGRAM......Page 153
4. CANFLEX DEMONSTRATION IRRADIATION......Page 157
REFERENCES......Page 161
1. BRIEF ANALYSIS OF WWER OPERATION......Page 162
3. RBMK FUEL CYCLE OPTIMIZATION AND HIGHER FUEL BURN-UP......Page 165
REFERENCES......Page 166
SEU/RU/THORIA FUELS (SESSION 3)......Page 167
RECYCLED URANIUM – AN ADVANCED FUEL FOR CANDU REACTORS......Page 168
4. OCCUPATIONAL HEALTH ASPECTS OF RU......Page 169
5. PROCESSING OF RU TO UO2 POWDER......Page 171
7. FUEL MANUFACTURE......Page 172
10. CONCLUSIONS......Page 174
REFERENCES......Page 175
2. METHOD OF ANALYSIS......Page 176
REFERENCES......Page 184
1. CALCULATION METHODOLOGY......Page 186
2. CELL PARAMETERS AND REACTIVITY EFFECTS......Page 187
3. EQUILIBRIUM POWER DISTRIBUTION AND REFUELING STRATEGIES......Page 194
4. SEU FUEL THERMALHYDRAULICS CONDITIONS EVALUATIONS......Page 201
5. THE REACTIVITY DEVICES PERFORMANCE EVALUATION......Page 202
6. SHUTDOWN SYSTEM PERFORMANCES......Page 204
REFERENCES......Page 206
1. INTRODUCTION......Page 208
2. CANFLEX AS THE REFERENCE CARRIER OF RU IN CANDU......Page 209
3. CANDU-6 REACTOR PHYSICS, THERMALHYDRAULICS, SAFETY AND FUEL PERFORMANCE OF CANFLEX-RU......Page 210
4. AVAILABILITY AND PROCESSING OF RU......Page 212
7. FUEL CYCLE COSTS FOR RU......Page 213
8. CONCLUSIONS......Page 214
REFERENCES......Page 215
1. INTRODUCTION......Page 217
3. OPTIONS FOR BURNING THORIUM IN CANDU REACTORS......Page 218
4. LATTICE PROPERTIES OF MIXED-THORIUM FUEL......Page 220
6. EFFECT OF FLUX-DEPENDENCE ON THORIUM PHYSICS CALCULATIONS......Page 224
REFERENCES......Page 226
1. INTRODUCTION......Page 227
2. RESULTS AND DISCUSSIONS......Page 229
REFERENCES......Page 232
MOX FUEL (SESSION 4)......Page 233
1. INTRODUCTION......Page 234
2. TECHNICAL OVERVIEW......Page 235
3. ECONOMIC OVERVIEW......Page 245
1. INTRODUCTION......Page 247
2. EXPERIMENTS AND RESULTS......Page 248
REFERENCES......Page 256
1. INTRODUCTION......Page 258
3. IRRADIATION OF BDL-419 MOX BUNDLES......Page 259
4. PIE RESULTS......Page 261
5. SUMMARY AND CONCLUSIONS......Page 263
REFERENCES......Page 264
1. INTRODUCTION......Page 265
2. ADVANCED LWR CORES FOR EFFECTIVE USE OF PLUTONIUM......Page 266
3. MOX CORE PHYSICS EXPERIMENTS......Page 272
REFERENCES......Page 276
1. W-Pu CONVERSION SAFETY......Page 277
2. SAFETY ISSUES FOR MOX FUEL FABRICATION FROM W-Pu......Page 278
REFERENCES......Page 279
INERT MATRIX (URANIUM-FREE) FUEL FOR ACTINIDE BURNING AND PLUTONIUM ANNIHILATION (SESSION 5)......Page 282
1. INTRODUCTION......Page 283
2. FUEL MATRIX......Page 284
3. FUEL ASSEMBLY DESIGN......Page 289
4. THE FUEL ASSEMBLY AS WASTE FORM......Page 294
REFERENCES......Page 296
1. INTRODUCTION......Page 298
2. ROX FUEL STUDIES......Page 299
3. SAFETY ANALYSIS AND PLUYONIUM ANIHILATION RATE......Page 304
4. ENVIRONMENTAL SAFETY ANALYSIS......Page 306
5. FUTURE R&D PROGRAM......Page 307
REFERENCES......Page 308
1. INTRODUCTION......Page 310
3. AECL'S PROGRAM......Page 311
4. REACTOR PHYSICS......Page 312
5. TANDEM ACCELERATORS TESTS......Page 316
7. COMPATIBILITY WITH WATER......Page 317
10. CONCLUSION......Page 318
REFERENCES......Page 319
INTRODUCTION......Page 320
I. CHOICE OF MATRICES......Page 321
II. THE TANOX DEVICE......Page 322
III. FIRST TANOX EXPERIMENTS USING CERCER AND CERMET RODS......Page 323
IV. EVALUATION OF THE CYCLE......Page 325
REFERENCES......Page 328
INTRODUCTION......Page 329
THE APA ASSEMBLY......Page 330
TEMPERATURE ASSESSMENT......Page 333
POSSIBLE SCENARIO......Page 334
REFERENCES......Page 337
LWR/HWR SYNERGISTIC FUEL CYCLES (SESSION 6)......Page 338
1. INTRODUCTION......Page 339
2. DUPIC SYSTEM ANALYSIS......Page 340
4. DUPIC CHALLENGES......Page 341
REFERENCES......Page 342
1. INTRODUCTION......Page 344
2. UNIQUE ASPECTS OF AN LWR - LWR RECYCLE PROGRAM......Page 345
3. ELIMINATING THE NEED FOR A SECOND REPOSITORY......Page 348
4. AN INTERNATIONAL DRY RECYCLE DEMONSTRATION PROGRAM......Page 349
REFERENCES......Page 350
1. INTRODUCTION......Page 352
3. PROGRESS......Page 353
4. FUTURE PLANS......Page 356
ACKNOWLEDGEMENTS......Page 357
LIST OF PARTICIPANTS......Page 358