Fuel failure in normal operation of water reactors : experience, mechanisms and management : proceedings of a Technical Committee meeting held in Dimitrovgrad, Russian Federation, 26-29 May 1992

COVER......Page 1
FOREWORD......Page 4
EDITORIAL NOTE......Page 5
CONTENTS......Page 6
Summary......Page 8
Recommendations......Page 10
Summary......Page 11
Summary......Page 12
Recommendations......Page 13
Summary......Page 14
Recommendations......Page 15
GENERAL OVERVIEW OF PRESENT STATUS OF EXPERIENCE (Session I)......Page 16
1.0 INTRODUCTION......Page 17
2.0 FAILURES THAT RELEASE ACTIVITY......Page 19
4.0 FAILURES UNLIKELY TO RELEASE ACTIVITY......Page 21
5.0 FUEL FAILURE STATISTICS......Page 22
REFERENCES......Page 25
INTRODUCTION......Page 26
2. FABRICATION OF FUEL......Page 27
3. MAJOR PERFORMANCE PARAMETERS AND STEADY-STATE FUEL CYCLES OF VVER-440 AND -1000......Page 28
5. OPERATION EXPERIENCE AND INCREASE OF VVER-440 FUEL BURN-UP......Page 30
6. OPERATION EXPERIENCE AND EXTENSION OF VVER-1000 FUEL BURN-UP......Page 33
References......Page 38
OPERATING EXPERIENCE OF RBMK FUEL UNDER NORMAL CONDITIONS AND ANALYSIS OF ITS DAMAGE CAUSES......Page 39
1. COOLANT ACTIVITY ANALYSIS......Page 46
2. ON-SITE FACILITIES FOR DETECTION AND EVALUATION OF THE LEAKING FUEL RODS......Page 47
3. CAUSES OF DEFECTS......Page 48
5. CONCLUSION......Page 49
1. SURVEY OF OPERATING EXPERIENCE......Page 50
2. CAUSES AND REMEDIES OF FUEL FAILURE AND DAMAGE......Page 52
4. STAGES OF FUEL FAILURE EVALUATION......Page 53
REFERENCES......Page 56
ABB ATOM FUEL FAILURE - AN OVERVIEW......Page 57
2. DETECTION AND CHARACTERIZATION OF FUEL FAILURES......Page 58
3. EXPERIENCE......Page 59
5. REMEDIES......Page 62
ACKNOWLEDGEMENTS......Page 63
DETECTION AND MONITORING OF FUEL FAILURES (Session II)......Page 64
1. PRINCIPLE OF CALCULATION METHODS......Page 65
REFERENCES......Page 69
2. Description of The FPMS......Page 70
3. Gneneral Criteria for The FPMS Compornents Installation......Page 75
4. Experience of The FPMS in Japanese Reactors......Page 76
1. INTRODUCTION......Page 77
2. EXPERIMENTAL DETAILS......Page 79
3. FUEL-ELEMENT DETERIORATION......Page 80
4. FISSION PRODUCT RELEASE......Page 88
5. POWER REACTOR APPLICATIONS......Page 92
ACKNOWLEDGEMENTS......Page 93
REFERENCES......Page 94
1. Introduction......Page 98
2. The Fuel Expert System features......Page 99
3. The results of the Fuel Expert System application at the Dukovany NPP......Page 102
References......Page 103
2. Reasons of poor performance of VVER-440 fuel rods produced in 1972-76......Page 104
3. Quantitative data on leaking VVER-440 and VVER-1000 fuel assemblies......Page 108
4. Data on number of leaking RBMK-1000 and RBMK-1500 fuel assemblies......Page 109
5. VVER reactor coolant activity......Page 110
FAILED FUEL MONITORING AT NUCLEAR POWER PLANTS WITH RBMK REACTORS: OPERATING PARAMETERS, REQUIREMENTS AND DECISION MAKING CRITERIA......Page 111
CAUSES AND MECHANISMS FOR FUEL FAILURE AND DAMAGE (Session III)......Page 116
1. INTRODUCTION......Page 117
2. FABRICATION DEFECTS......Page 118
3. PELLET/CLADDING INTERACTION (PCI) DEFECTS......Page 119
4. FRETTING AND VIBRATION DEFECTS......Page 120
5. PRIMARY HYDRIDING DEFECTS......Page 122
REFERENCES......Page 123
2. Reactor operation......Page 124
3. Inspection......Page 125
4. Cause of failure......Page 127
5. Countermeasures......Page 128
1. BACKGROUND......Page 129
3. EXAMINATION RESULTS......Page 130
4. CORRECTIVE ACTIONS FOR DEBRIS-INDUCED FRETTING......Page 131
5. DEBRIS CHARACTERISTICS......Page 132
7. SUMMARY......Page 133
2.0 STATISTICS OF DEBRIS FAILURE AND SURVEY OF EXPERIENCE......Page 134
3.0 VISUAL APPEARANCE OF DEBRIS FRETTING FAILURES......Page 135
4.0 DEBRIS SOURCES......Page 136
5.0 DEBRIS PREVENTION......Page 137
6.0 DEBRIS RESISTANT FUEL DESIGN FEATURES......Page 138
MANAGEMENT OF FAILED FUEL (Session IV)......Page 140
2} CONDITIONS FOR RE-INSERTION......Page 141
4) RE-INSERTED DEFECTS BEHAVIOUR......Page 142
5) STATUS AFTER 10 YEARS OF EXPERIENCE......Page 144
6) CONCLUSION......Page 145
1. Criteria of FA depressurization estimate during the reactor operation......Page 146
2. Main causes of the VVER reactor fuel leakage......Page 147
4. Conclusions......Page 149
2. KKL fuel failure power history.......Page 150
3. Detection of defect fuel......Page 152
4. Failed Fuel Inspection results......Page 155
5. Post-irradiation handling of failed fuel......Page 159
6. KKL Failed Fuel Management......Page 160
7. Conclusion and summary......Page 161
1. INTRODUCTION......Page 162
3. PRIMARY CIRCUIT ACTIVITY EVOLUTION......Page 163
4. POOLSIDE EXAMINATION......Page 164
5 . HISTORY OF FUEL FAILURE......Page 166
6 ACTIVITY RELEASES RESULTING FROM U and MOX FUEL ROD FAILURES......Page 167
REFERENCES......Page 169
SPECIFIC EXPERIMENTAL APPROACHES (Session V)......Page 170
1. INTRODUCTION:......Page 171
5. PERFORMANCE OF THE EXPERIMENT - MAIN FINDINGS :......Page 172
6. METALLOGRAPHIC POST IRRADIATION EXAMINATIONS :......Page 174
7. CONCLUSIONS :......Page 175
1. BACKGROUND INFORMATION......Page 176
2. OUTLINE OF THE STUDSVIK FUEL TEST SCHEME......Page 178
3. EXPLORATORY TESTING OF PROMOTED/SUPPRESSED HYDRIDING......Page 180
4 A PROPOSED INTERNATIONAL PROGRAM......Page 182
REFERENCES......Page 183
EXPERIMENTAL STUDY ON THE WWER FUEL BEHAVIOR IN RESEARCH REACTORS AND SHIELDED HOT CELLS......Page 184
2. Methodical basis of the program and some data on the investigation experience......Page 185
REFERENCES......Page 196
1. UPGRADING FUEL ASSEMBLIY DESIGNS......Page 197
2. MAJOR DIRECTIONS IN IMPROVEMENT OF OPERATION RELIABILITY OF FUELS......Page 198
3. RESULTS and DISCUSSION......Page 203
REFERENCES......Page 206
POSTER SESSION......Page 207
1. Water method......Page 208
5. Dry method......Page 209
Introduction......Page 210
Methodics and measuring results......Page 211
Reference......Page 215
MEASUREMENT METHODS OF GAS FISSION PRODUCTS QUANTITY UNDER FUEL ELEMENT CLADDINGS BY MEANS OF DEEP COOLING......Page 216
INVESTIGATIONS OF RADIOACTIVE FISSION PRODUCT RELEASE FROM FUEL ELEMENTS WITH INITIAL CLADDING DEFECTS DURING OPERATION OF THE VK-50 REACTOR......Page 219
METHOD FOR CALCULATING FISSION PRODUCT RELEASE FROM THE FUEL CLADDING GAP OF A FAILED FUEL ELEMENT TO THE COOLANT......Page 224
SOME RESULTS OF POST-IRRADIATION INVESTIGATIONS OF VVER-1000 UNSEALED FUEL ASSEMBLY......Page 229
RESULTS OF POST-REACTOR INVESTIGATIONS OF VVER-1000 UNTIGHT FUEL ASSEMBLY......Page 231
1. INTRODUCTION......Page 237
2. EXPERIMENTAL MEANS AND METHODS......Page 238
3 EXPERIMENTAL RESULTS......Page 239
4. DISCUSSION......Page 242
REFERENCES......Page 245
2. IODINE-ZR CLADDING INTERACTION IN SCC......Page 246
3 EMBRITTLEMENT MODELS OF I Zr INTERACTION......Page 247
4. INFLUENCE OF STRESSES ON CRACK GROWTH IN IODINE ENVIRONMENT......Page 248
5. RATE OF IODINE INDUCED CRACK GROWTH......Page 249
6. CRACK NUCLEATION AT INNER FUEL CL ADDING SURFACE......Page 251
7. INFLUENCE OF IRRADIATION ON CLADDING IODINE CORROSION RESISTANCE......Page 252
REFERENCES......Page 253
1. Processes of Clad Failure and the Fission Product Leakage Model......Page 254
2. Structural-Dinamic Analysis of Damage Reasons......Page 257
REFERENCES......Page 262
1. VVER Fuel......Page 263
2. RBMK Fuel......Page 268
References......Page 272
INFLUENCE OF WATER CHEMISTRY REGIMES ON FUEL CLADDING FAILURE IN LWRs......Page 273
References......Page 276
LIST OF PARTICIPANTS......Page 277