Safety of nuclear installations : future direction

COVER......Page 1
FOREWORD......Page 3
EDITORIAL NOTE......Page 4
CONTENTS......Page 5
The Window of Opportunity......Page 9
The Need for Nuclear Power: A Quantitative Perspective......Page 10
Demonstrating Safety......Page 11
Building Public Confidence......Page 13
Towards a Higher Radiation Literacy......Page 14
OPENING SESSION......Page 17
INTRODUCTORY REMARKS......Page 18
SAFETY OF NUCLEAR INSTALLATIONS OF THE NEXT GENERATION AND BEYOND......Page 20
CONCLUSION......Page 26
INDUSTRY LEADERS AND MORE FACTS: WELCOME TO BOTH......Page 27
ENVIRONMENTAL IMPACT OF FOSSIL FUEL ENERGY TECHNOLOGIES (Session I)......Page 29
1. INTRODUCTION......Page 30
2. GREENHOUSE GASES......Page 31
3. FUTURE TREND IN GLOBAL ATMOSPHERIC POLLUTION......Page 32
4. THE GREENHOUSE EFFECT......Page 33
5. THE STEADY-STATE RESPONSE......Page 34
6. PREDICTING THE TRANSIENT CLIMATIC CHANGE......Page 35
7. PREDICTING SEA LEVEL RISE......Page 36
8. IMPACTS OF CLIMATE CHANGE......Page 37
REFERENCES......Page 39
2.0 FOSSIL FUEL EMISSIONS......Page 40
3.1 Atmospheric Transformations......Page 42
3.2 Atmospheric Removal Mechanisms......Page 43
3.3 Atmospheric Transport Processes......Page 44
3.4 Ambient Concentration Levels......Page 45
4.0 EFFECTS OF ACID DEPOSITION......Page 46
4.2 Materials Degradation Effects......Page 47
4.4 Landscape Acidification Effects......Page 48
6.0 CONCLUSIONS......Page 49
REFERENCES......Page 50
SPECIAL INVITED PRESENTATION......Page 52
2.1 Sources and Effects of Acid Rain......Page 57
2.4 USA Plans......Page 58
3.3 An Agenda for Action in the Next Decade......Page 59
THE GREENHOUSE EFFECT AND ACIDIFICATION......Page 60
FUTURE NEEDS FOR NUCLEAR POWER (Session II)......Page 62
1. Introduction......Page 63
2. The IIASA Low Scenario as a reference......Page 64
3. The Colombo and Goldemberg Energy Conservation Scenarios......Page 67
4. Technical elements for a reduction of CO2 emissions......Page 70
5. The 1989 Jülich CO2 reduction scenario......Page 72
6. 3.7 TWyears/year of nuclear energy......Page 74
References......Page 75
MAIN ISSUES REQUIRING RESOLUTION FOR LARGE SCALE DEPLOYMENT OF NUCLEAR ENERGY......Page 77
SAFETY APPROACH EVALUATION FOR FUTURE LIGHT WATER POWER PLANTS......Page 89
Have vs have-not nations......Page 92
Recent trends of public opinion for nuclear energy......Page 93
1. DEMAND......Page 94
3. ALTERNATIVES......Page 95
5. A WORLD OF FEELINGS. A WORLD OF REALITIES......Page 96
7. THE NUCLEAR POWER QUOTA......Page 97
8. NEEDS OF THE NUCLEAR ALTERNATIVE......Page 98
3. ARGUMENTS AGAINST NUCLEAR POWER......Page 100
4. WHY EFFICIENCY IS NOT ENOUGH......Page 101
5. FUTURE DEMAND GROWTH......Page 102
References......Page 103
GLOBAL ENERGY DEMAND......Page 104
ELECTRICITY DEMAND AND NUCLEAR POWER......Page 105
SAFETY OBJECTIVES (Session III)......Page 108
INTRODUCTION......Page 109
OBJECTIVES FOR AN UNSURE PUBLIC......Page 111
LOW LEVEL RADIATION AS A FACT OF LIFE......Page 112
IMPACT OF LOW LEVEL RADIATION......Page 113
The health effects......Page 114
The regulatory Units......Page 115
The health risk......Page 116
The accident risk......Page 117
PROPOSALS......Page 119
CONCLUSION......Page 120
Introductory Comments.......Page 121
General Features of the Document.......Page 122
Fundamental Principles.......Page 123
Application to Plants of Future Types.......Page 125
2. SAFETY CULTURE AND INSTITUTIONAL QUALITY ASSURANCE......Page 127
6. OBJECTIVES AND PRINCIPLES FOR THE NEXT GENERATION OF NUCLEAR POWER PLANTS......Page 128
REFERENCES......Page 129
SOME GENERAL IDEAS FOR DISCUSSION ON THE SUBJECT OF SAFETY GOALS AND OBJECTIVES......Page 130
SAFETY OBJECTIVES (continued) (Session IV)......Page 134
1. INTRODUCTION......Page 135
2. CRITERIA FOR DESIGNERS......Page 136
3. GAIN PUBLIC ACCEPTANCE......Page 138
4. ISSUES FOR DESIGNERS......Page 140
5. PEOPLE......Page 143
6. PUBLIC ACCEPTANCE......Page 144
7. SUMMARY......Page 146
REFERENCES......Page 147
ONE UTILITY'S POINT OF VIEW......Page 148
SAFETY LEVELS - SATISFACTORY BUT STILL PERFECTIBLE......Page 149
CHOOSING THE NEXT TYPE OF REACTOR - SAFETY OF FUTURE REACTORS......Page 153
PREREQUISITES FOR SUCCESS......Page 156
CONCLUSION......Page 158
2. Some Safety Objective-Goals for Large Scale Deployment......Page 160
Avoidance and Mitigation of Severe Accidents by......Page 162
SAFETY OBJECTIVES FOR LARGE-SCALE DEPLOYMENT OF NUCLEAR POWER......Page 164
1. INTRODUCTION......Page 165
3. TOLERABILITY OF RISK......Page 166
4 HUMAN FACTORS......Page 167
6. CONCLUDING REMARKS......Page 169
REFERENCES......Page 170
APPLICATION OF SAFETY OBJECTIVES TO SAFETY STANDARDS AT THE NEXT STAGES OF NUCLEAR POWER DEPLOYMENT......Page 171
SAFETY ASPECTS OF THE NEXT GENERATION OF CURRENT-TYPE NUCLEAR POWER PLANTS (Session V)......Page 174
2. Establishing the Requirements......Page 175
3. Charting the Course for CANDU......Page 178
4. Specific Examples......Page 180
5. Concluding Remarks......Page 181
References......Page 182
1. INTRODUCTION : FOR A GLOBAL SAFETY......Page 183
2. FEED-BACK OF EXPERIENCE : THE CASE FOR N4......Page 186
3. WHERE DO WE GO FROM HERE ?......Page 187
4. WHAT, THEN ?......Page 188
REFERENCES......Page 190
1. INTRODUCTION......Page 191
2. GENERAL REMARKS ABOUT INHERENT AND PASSIVE SAFETY......Page 192
3. PROBABILISTIC RISK ANALYSIS AS A GUIDING INSTRUMENT FOR IDENTIFYING SAFETY IMPROVEMENT NEEDS......Page 193
4 1 ADVANCED SAFETY CHARACTERISTICS OF THE 1300 MW KONVOI NPP GENERATION......Page 195
4.2 INNOVATIONS IN ADVANCED INSTRUMENTATION AND CONTROL (I & C) SYSTEMS USING MICROPROCESSOR-BASED DIGITAL TECHNOLOGY......Page 199
4.3 PREVENTIVE ACCIDENT MANGEMENT MEASURES TO MAINTAIN REACTOR PRESSURE VESSEL INTEGRITY IN BEYOND DESIGN EVENTS......Page 200
4.4 MITIGATIVE ACCIDENT MANAGEMENT MEASURES TO MAINTAIN CONTAINMENT INTEGRITY IN BEYOND DESIGN EVENTS......Page 203
5. SIEMENS/KWU BOILING WATER REACTORS......Page 205
REFERENCES......Page 206
1. INTRODUCTION......Page 208
2. SURVEY STUDY......Page 210
3. CONCEPTUAL DESIGN......Page 217
ACKNOWLEDGEMENTS......Page 218
1. INTRODUCTION......Page 219
3. APPROACHES TO SAFETY ANALYSIS......Page 220
4. ACCIDENT SEQUENCE IDENTIFICATION METHOD......Page 221
5. APPLICATION TO ADVANCED DESIGNS......Page 222
6. IMPLICATIONS FOR SAFETY ANALYSIS......Page 223
7. CONCLUSIONS......Page 224
1. INTRODUCTION......Page 225
2. FUNDAMENTAL TRENDS IN WER NPP SAFETY AND RELIABILITY IMPROVEMENT......Page 226
3.1 REACTOR UPGRADING......Page 227
3.2 BORON INJECTION SYSTEM......Page 228
3.3 PASSIVE HEAT REMOVAL SYSTEM WITH LOSS OF ALL POWER SUPPLY SOURCES......Page 229
3.5 SYSTEM FOR PRESSURE SUPRESSION AND CLEAN-UP OF ACCIDENTAL RELEASES......Page 235
3.7 SYSTEM FOR CONTAINING AND COOL-DOWN OF MELT CORE OUTSIDE THE REACTOR VESSEL (CORE CATCHER)......Page 237
4. CONCLUSION......Page 238
1. INTRODUCTION......Page 240
2. IMPROVED SAFETY OBJECTIVES......Page 241
3. PASSIVELY SAFE DESIGNS......Page 242
REFERENCES......Page 247
1. INTRODUCTION......Page 248
2. CONCLUSIONS......Page 257
REFERENCES......Page 258
SAFETY ASPECTS OF NEW DESIGNS AND CONCEPTS FOR NUCLEAR POWER PLANTS (Session VI)......Page 259
1. INTRODUCTION......Page 260
2. DESIGN APPROACH......Page 261
3.1. Unprotected transients......Page 263
3.2. Decay heat removal......Page 264
3.3 Core support structures......Page 265
3.4. Containment......Page 266
5. CONCLUSIONS......Page 267
1. INTRODUCTION......Page 268
Safety Goal Policy......Page 269
3. INTEGRAL FAST REACTOR PROGRAM AT ANL......Page 270
IFR Fuel Thermal Performance......Page 271
IFR Fuel Local Faults Tolerance......Page 272
Anticipated Transients Without Scram......Page 273
4. IFR FUEL CYCLE - ACTINIDE RECYCLE......Page 274
Safety Approach......Page 275
Innovative Plant and Safety Features......Page 276
NRC Regulatory Review of the ALMR......Page 279
REFERENCES......Page 281
INTRODUCTION......Page 283
1. CONCEPTS OF FAST REACTOR POWER UNITS WITH INCREASED SAFETY AND FEASIBLY ATTAINABLE SAFETY......Page 284
2. The BN-800 Power Unit Safety......Page 288
3. Some Conclusion Notes......Page 291
1. INTRODUCTION......Page 293
2. DESIGN GOALS AND SAFETY CONCEPT - THE INDUSTRIAL PROGRAMME......Page 294
3. ADVANCED SAFETY PHILOSOPHY, INDEPENDENT SAFETY ASSESSMENT - THE SCIENTIFIC PROGRAMME......Page 302
4. UNCERTAINTIES, DEMONSTRATION OF PHYSICAL PROPERTIES - A CONCLUDING OUTLOOK......Page 305
REFERENCES......Page 307
SAFETY ASPECTS OF THE MODULAR HIGH-TEMPERATURE GAS-COOLED REACTOR (MHTGR)......Page 308
INTRODUCTION AND DESIGN OVERVIEW......Page 309
SAFETY PHILOSOPHY......Page 312
TOP-LEVEL REGULATORY CRITERIA AND USER SAFETY REQUIREMENTS......Page 313
LICENSING BASIS EVENTS......Page 314
SAFETY DESIGN APPROACH AND RESULTS......Page 315
Remove Core Heat......Page 316
Control Chemical Attack......Page 319
SAFETY IMPORTANCE OF OPERATOR ACTIONS......Page 320
REFERENCES......Page 322
SPECIAL INVITED PRESENTATION: PUBLIC ACCEPTANCE OF NUCLEAR POWER......Page 324
SPECIAL SAFETY ISSUES: SAFETY ASPECTS OF NEW DESIGNS AND CONCEPTS FOR NUCLEAR POWER PLANTS (continued) (Session VII)......Page 327
1. INTRODUCTION......Page 328
2. INTERNAL FIRES......Page 329
3. HIGH WINDS/TORNADOES......Page 332
4. EXTERNAL FLOODS......Page 333
6. SEISMIC......Page 334
7. SOME PERSONAL COMMENTS......Page 336
REFERENCES......Page 337
1. INTRODUCTION......Page 339
2.2 Melt through of the pressure vessel under high system pressure......Page 340
3. THE PROBLEM OF H2-DETONATION IN THE REACTOR CONTAINMENT......Page 341
4. STEAM EXPLOSION......Page 343
5.1 Control of the ex-vessel coremelt......Page 344
6. NEW OUTER CONTAINMENT DESIGN......Page 345
7. CONCLUSIONS......Page 347
REFERENCES......Page 348
INTRODUCTION......Page 350
A. SEOCND GENERATION MAN/MACHINE INTERFACES......Page 351
B. THIRD GENERATION MAN/MACHINE INTERFACES......Page 353
REFERENCES......Page 361
Introduction......Page 363
Nuclear-Engineering Peculiarities Assuring Reactor Plant Safety......Page 364
Safety Concept......Page 365
Safety Analysis......Page 367
Conclusion......Page 371
APPENDIX - PRINCIPLES IMPORTANT FOR SAFETY PROVISIONS IMPLEMENTED IN THE AST REACTOR PLANT......Page 373
1. THE NEED FOR NUCLEAR HEATING......Page 376
2.1 Design Requirements......Page 377
2.2 Public Perception and Public Acceptance......Page 378
2.3 Safety Principles and Licensing......Page 379
3. APPLICATIONS: LARGE CENTRALIZED PLANTS......Page 381
4.1 SLOWPOKE Heating Reactor as an Example......Page 382
4.2 Worldwide Small Heating Reactors......Page 384
5. CONCLUSIONS......Page 386
REFERENCES......Page 387
SAFETY ASPECTS OF NEW DESIGNS AND PROCESSES FOR THE NUCLEAR FUEL CYCLE (Session VIII)......Page 389
I - INTRODUCTION......Page 390
II - GENERAL RULES AND METHODOLOGY......Page 391
Ill - THE TECHNOLOGICAL STEPS OF THE CYCLE BEFORE THE REACTOR......Page 392
IV - THE TECHNOLOGICAL STEPS OF THE CYCLE AFTER THE REACTOR......Page 395
V - GENERAL CONCLUSION......Page 399
ACKNOWLEDGEMENTS......Page 400
SAFETY ASPECTS OF THE IFR PYROPROCESS FUEL CYCLE......Page 401
Fission Gas Release Due to Loss of Cell Atmosphere......Page 406
Metal Fire in Argon Cell......Page 407
Meltdown of Fuel Assembly in a Storage Pit......Page 409
Facility Fires and Explosions......Page 411
Other Accidents......Page 412
Summary......Page 414
REFERENCES......Page 415
2. REPOSITORY CONCEPT......Page 417
3. FUEL MATRIX......Page 418
5. BUFFER, BACKFILL, AND SEALING OF REPOSITORY......Page 420
6. ROCK STABILITY AND GROUNDWATER MOBILITY......Page 422
8. SAFETY CRITERIA......Page 423
9. SAFETY ASSESSMENT......Page 424
REFERENCES......Page 425
1. INTRODUCTION......Page 426
2. CHARACTERISTICS OP USED CANDU FUEL......Page 428
3. CHARACTERISTICS OF PLUTONIC ROCK MASSES......Page 430
4. DISPOSAL CONCEPT......Page 433
5.1 The Used-Fuel Container......Page 435
5.2 The Uranium Oxide Fuel......Page 436
5.3 The Sealing and Backfilling Materials......Page 437
REFERENCES......Page 438
FUEL CYCLE SAFETY EVALUATION......Page 440
CLOSING PANEL......Page 442
1. PRIMARY REFERENCE POINTS IN ITALY......Page 443
2. ACTIVITIES AND TRENDS......Page 444
3. A FINAL REMARK......Page 445
REFERENCES......Page 446
WHERE DO WE GO FROM HERE?......Page 447
STATUS AND TRENDS IN NUCLEAR POWER DEVELOPMENT IN THE UNION OF SOVffiT SOCIALIST REPUBLICS......Page 450
POSTER PRESENTATIONS......Page 460
1. OPERATING PRINCIPLE......Page 461
2. CORE PROTECTION......Page 466
4. CONTAINMENT......Page 467
6. PLANT OPERATION......Page 468
9. CONCLUSION......Page 470
REFERENCES......Page 471
2. THE BACKGROUND......Page 472
3. THE FLOODED STACK-OF-BEAMS (SOB) CONCEPT......Page 473
3.1 The SOB structure and its interaction with the corium......Page 474
3.3 Long Term Cooling......Page 476
4. THE APPLICATIONS......Page 477
5. THE STEAM EXPLOSION ISSUE......Page 478
6.1 Pressure and Temperature transients in the containment......Page 479
6.2 Temperature transients in the SS beams......Page 480
REFERENCES......Page 481
TERMINOLOGY FOR FUTURE NUCLEAR POWER PLANTS......Page 482
1. INTRODUCTION......Page 483
2.1 Inherent safety......Page 484
2.2 Passive safety......Page 486
2.3 Grace period/walkaway safe......Page 490
3.1 Inherent and passive safety plants......Page 491
3.2 Reference bounding events......Page 493
4. REVISION AND NEW DEFINITIONS OF TERMS......Page 494
APPENDIX - PROPOSAL FOR CATEGORIZATION OF PASSIVE FUNCTIONS AND OF SYSTEMS OR COMPONENTS......Page 496
1. INTRODUCTION......Page 502
3. SBWR PERFORMANCE AND SAFETY ANALYSES......Page 503
REFERENCES......Page 509
1. INTRODUCTION......Page 511
2. CANDU EVOLUTION......Page 512
2.I Simplification......Page 513
2.2 Safety......Page 514
3,1 Design Objectives......Page 515
3.2 Safety......Page 516
5.1 Passive Safeguards for LOCA Events......Page 517
5.2 Passive Safeguards for Non- LOCA Events......Page 521
5.3 Passive Safeguards Containment......Page 523
References;......Page 525
2.2 Monitor Computers CBmce)......Page 527
2.3 Trip Computers (CANDU 6)......Page 528
2.4 Fully Computerized Shutdown System (Darlington^......Page 530
3. FAULT TOLERANT AND FAIL SAFE DESIGN......Page 531
3.3 Defensive Programming......Page 532
5.3 The Scheduling Algorithm......Page 533
6.5 Verification and Validation (V & V^......Page 534
7.1 Unit Testing......Page 535
8.1 Performance Record......Page 536
9. BENEFITS OF THE COMPUTERIZED DESIGN......Page 537
REFERENCES......Page 538
SAFETY RECOMMENDATIONS FOR ADVANCED REACTORS IN THE NETHERLANDS......Page 540
2. SOURCE TERM RECOMMENDATIONS......Page 541
3. THE GOVERNMENT'S RISK ASSESSMENT POLICY......Page 542
4. INHERENT AND PASSIVE SAFETY FEATURES IN THE DESIGN OF NUCLEAR POWER PLANTS......Page 543
4.1. BASIC SAFETY PRINCIPLES......Page 544
5.1. DEFENCE IN DEPTH......Page 547
5.2. SINGLE FAILURE CRITERION......Page 548
5.3. HUMAN ACTION......Page 549
6. THE SBWR AND THE GKN (DODEWAARD) NUCLEAR POWER PLANT......Page 550
7. CONCLUSIONS......Page 551
REFERENCES......Page 552
THE SAFE INTEGRAL REACTOR Development for the next generation......Page 553
2. Basic Design Criteria......Page 554
3. Technical Description......Page 555
4. The SIR Module......Page 556
5. Reactor Core......Page 558
7.1 Pumps......Page 560
8.1 Emergency Core Cooling System (ECCS)......Page 561
9. Containment and its Safety Systems......Page 562
10.2 Simplicity of safety systems......Page 564
12. Summary and Conclusions......Page 565
REFERENCES......Page 566
2. THE WESTINGHOUSE AP600......Page 567
5. SIMPLIFICATION: PASSIVE COOLANT REPLENISHMENT AND REMOVAL OF DECAY HEAT......Page 568
6. SIMPLIFICATION: REMOVAL OF DECAY HEAT FROM THE CONTAINMENT......Page 569
8. AP600: ECONOMICAL AND COMPETITIVE......Page 570
9. AP600: PUBLIC ACCEPTANCE AND LICENSABILITY......Page 573
1. INTRODUCTION......Page 574
2. RETENTION OF FISSION PRODUCTS......Page 575
3. REMOVAL OF AFTER-HEAT BY MACHINES OR BY INHERENT MEANS......Page 576
4. SHAPE OF THE CORE IN VIEW OF PASSIVE AFTER-HEAT REMOVAL......Page 578
5. 750 MW HIGH-TEMPERATURE REACTOR WITH A PLATE SHAPED CORE......Page 579
REFERENCES......Page 583
1. INTRODUCTION......Page 584
2. THE LOBI-MOD2 EXPERIMENTAL PROGRAMME......Page 585
3. THE LOBI-MOD2 TEST FACILITY......Page 586
4. ASPECTS OF PWR PASSIVE SAFETY......Page 588
5. LOBI-MOD2 PCS PASSIVE BLEED AND FEED......Page 589
6. LOBI-MOD2 PORV OPERATION IN SMALL BREAK LOCA......Page 592
REFERENCES......Page 596
1. INTRODUCTION......Page 598
2.1 ESTIMATION OF NPP LARGE ACCIDENTS SOCIAL DAMAGE......Page 599
3. SAFETY DEMANDS TO NUCLEAR REACTORS OF NEW GENERATION......Page 600
4. WAYS TO MEET SAFETY DEMANDS......Page 601
4.2 RESIDUAL SHUTDOWN HEAT AND RADIOACTIVITY STORED IN THE CORE......Page 602
4.3 STORED NON-NUCLEAR ENERGY......Page 603
4.4 QUALITATIVE LEVELS TO MEET SAFETY REQUIREMENTS......Page 604
REFERENCES......Page 606
SUMMARY OF THE WORKSHOP......Page 607
CHAIRMEN OF SESSIONS......Page 615
SECRETARIAT OF THE WORKSHOP......Page 616
LIST OF WORKSHOP PARTICIPANTS......Page 617
LIST OF PANEL PARTICIPANTS......Page 635