Review of fuel failures in water cooled reactors:
Gespeichert in:
Format: | Buch |
---|---|
Sprache: | English |
Veröffentlicht: |
Vienna
IAEA
1998
|
Schriftenreihe: | International Atomic Energy Agency: Technical reports series
388 |
Schlagworte: | |
Online-Zugang: | Inhaltsverzeichnis |
Beschreibung: | 167 S. Ill., graph. Darst. |
ISBN: | 9201022980 |
Internformat
MARC
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245 | 1 | 0 | |a Review of fuel failures in water cooled reactors |c International Atomic Energy Agency |
246 | 1 | 3 | |a STI DOC 010 388 |
264 | 1 | |a Vienna |b IAEA |c 1998 | |
300 | |a 167 S. |b Ill., graph. Darst. | ||
336 | |b txt |2 rdacontent | ||
337 | |b n |2 rdamedia | ||
338 | |b nc |2 rdacarrier | ||
490 | 1 | |a International Atomic Energy Agency: Technical reports series |v 388 | |
650 | 7 | |a Combustibles nucleares |2 embne | |
650 | 4 | |a Nuclear fuel elements | |
650 | 4 | |a System failures (Engineering) | |
650 | 4 | |a Water cooled reactors | |
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Datensatz im Suchindex
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adam_text | CONTENTS
1.
INTRODUCTION
......................................... 1
References
.............................................. 2
2.
HISTORICAL REMARKS ON FUEL FAILURE
AND DESIGN EVOLUTION
................................ 3
2.1.
Fuel failures
......................................... 3
2.2.
Fuel design evolution
.................................. 5
2.2.1.
BWRs
......................................... 5
2.2.2.
PWRs
......................................... 5
2.2.3.
WWERs
....................................... 6
2.2.4.
CANDUs
....................................... 6
2.3.
Fuel types in operation
................................. 7
References
.............................................. 9
3.
WORLD OVERVIEW ON FUEL FAILURES IN
1987-1994 ........ 9
3.1.
Measuring fuel reliability
............................... 9
3.1.1.
Coolant activity levels
............................ 10
3.1.2.
LWR fuel failure rates
............................ 10
3.1.3.
CANDU fuel failure rates
.......................... 13
3.1.4.
Comparison of CANDU
and LWR fuel failure rates
......................... 14
3.2.
Average fuel failure rates
............................... 14
3.2.1.
Regional averages
................................ 15
3.2.2.
Evolution of world averages
........................ 22
3.3.
Distribution of failure causes
............................. 25
3.3.1.
Regional distributions
............................. 25
3.3.2.
Estimate of world averages
......................... 30
3.3.3.
Discussion
..................................... 32
3.4.
Distribution of failure occurrences
........................ 33
3.4.1.
Regional examples
............................... 33
3.4.2.
Multiple failure incidents/defect excursions
............ 34
3.4.3.
Impact of multiple failure incidents
on the failure statistics
............................ 36
References
.............................................. 37
4.
DETECTION,
EXAMINATION
AND ANALYSIS OF FUEL FAILURES
........................ 40
4.1.
Introduction
......................................... 40
4.2.
Evaluation of coolant activity
............................ 40
4.2.1.
Background
.................................... 40
4.2.2.
Leaker diagnostics
............................... 42
4.2.3.
Leaker estimates
................................. 45
4.2.4.
Burnup estimates: the 134C/137C activity ratio
........... 50
4.3.
Localization of fuel failures
.............................. 51
4.3.1.
Sipping procedures
............................... 51
4.3.2.
Locating and identifying failed
fuel in CANDU reactors
.......................... 54
4.3.3.
Ultrasonic testing
................................ 56
4.3.4.
Flux tilting (BWRs)
.............................. 56
4.4.
Fuel examination
...................................... 57
4.4.1.
Poolside inspection techniques
...................... 57
4.4.2.
Hot cell examinations
............................. 59
4.5.
Fuel failure analysis
................................... 60
4.5.1.
Background
.................................... 60
4.5.2.
Manufacturing and handling
........................ 61
4.5.3.
Operation and design
............................. 62
References
.............................................. 62
5.
MECHANISMS AND ROOT CAUSES OF FUEL FAILURES
....... 65
5.1.
Introduction
......................................... 65
5.2.
Manufacturing defects
.................................. 69
5.2.1.
General background
.............................. 69
5.2.2.
Leaking end plugs
............................... 70
5.2.3.
Welding defects
................................. 70
5.2.4.
External local hydriding due to
Ni
contamination of the cladding surface
................ 72
5.2.5.
Insufficient volume of fuel element (CANDU fuel)
....... 74
5.3.
Primary hydriding
..................................... 74
5.3.1.
General background
.............................. 74
5.3.2.
Failure mechanisms
.............................. 75
5.4.
PCI (pellet-cladding interaction)
.......................... 77
5.4.1.
General background
.............................. 77
5.4.2.
Failure mechanism
............................... Xl
5.4.3.
PCI failure during abnormal transients
................ 85
5.4.4.
Other potential detect causes
....................... 86
5.4.5.
Corrective actions
................................ 86
5.5.
Corrosion
........................................... 90
5.5.1.
General background
.............................. 90
5.5.2.
Excessive corrosion
.............................. 90
5.5.3.
CILC failure
.................................... 93
5.5.4.
Influence of transient water chemistry
and cladding material on CILC failure
................ 95
5.5.5.
Corrosion failure caused by cladding susceptibility
and irregular water chemistry
....................... 97
5.5.6.
Corrosion by carbon-containing
crud
................. 98
5.5.7.
Local concentration of corrosion hydrogen (suspect)
..... 100
5.6.
Dryout
............................................. 100
5.6.1.
General background
.............................. 100
5.6.2.
Failure mechanism
............................... 101
5.7.
Grid-rod fretting
...................................... 102
5.7.1.
General background
.............................. 102
5.7.2.
Fabrication and design related failures
................ 103
5.7.3.
Fluid-elastic instability by cross-flow
................. 104
5.7.4.
Flow induced assembly vibration
.................... 106
5.8.
Fretting by debris
..................................... 108
5.8.1.
General background
.............................. 108
5.8.2.
Debris characteristics
............................. 108
5.8.3.
Corrective actions
................................ 110
5.9.
Baffle jetting
......................................... 113
5.9.1.
Fuel failure by baffle jetting
........................ 113
5.9.2.
Corrective measures
.............................. 114
5.10.
Assembly damage
..................................... 1 15
5.10.1.
Assembly bow
................................. 115
5.10.2.
Mechanical damage during handling
................. 119
5.10.3.
Miscellaneous damage
........................... 119
References
.............................................. 121
6.
SECONDARY FUEL FAILURES
............................. 128
6.1.
Types of secondary fuel failures
.......................... 128
6.2.
Mechanism of secondary hydriding
........................ 130
6.2.1.
General background
.............................. 130
6.2.2.
Fuel rod deterioration by secondary hydriding
(without crack growth)
............................ 131
6.2.3.
Factors
affecting secondary hydriding
................ 133
6.2.4.
In-pile secondary damage test
....................... 137
6.3.
Severe degradation
.................................... 137
6.3.1.
General background
.............................. 137
6.3.2.
Failure degradation with excessively
high off-gas release
.............................. 138
6.3.3.
Degradation mechanism
........................... 141
6.3.4.
Prevention of severe degradation
..................... 148
References
.............................................. 149
7.
FUEL FAILURE PREVENTION AND MANAGEMENT
IN PLANT OPERATION
.................................... 151
7.1.
Existing operating limits and recommended practices
.......... 151
7.1.1.
Coolant and off-gas activity
........................ 151
7.1.2.
Guidelines for power changes
and load following operation
....................... 152
7.1.3.
Guidelines for prevention of severe degradation
......... 153
7.1.4.
Water chemistry controls
.......................... 154
7.1.5.
Fuel loading/unloading practices
..................... 157
7.1.6.
Current practice for handling, storage
and disposal of failed fuel
......................... 158
7.2.
Reuse of failed LWR fuel
............................... 158
7.2.1.
Experience with controlled reinsertion
of leaking fuel
.................................. 158
7.2.2.
Behaviour of reinserted defects
...................... 160
7.2.3.
Experience with repaired and reconstituted fuel
......... 161
References
.............................................. 162
8.
CONCLUSIONS AND RECOMMENDATIONS
.................. 163
CONTRIBUTORS TO DRAFTING AND REVIEW
.................... 167
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genre | (DE-588)1071861417 Konferenzschrift gnd-content |
genre_facet | Konferenzschrift |
id | DE-604.BV012162220 |
illustrated | Illustrated |
indexdate | 2024-07-09T18:22:47Z |
institution | BVB |
isbn | 9201022980 |
language | English |
oai_aleph_id | oai:aleph.bib-bvb.de:BVB01-008238762 |
oclc_num | 41319736 |
open_access_boolean | |
owner | DE-91 DE-BY-TUM |
owner_facet | DE-91 DE-BY-TUM |
physical | 167 S. Ill., graph. Darst. |
publishDate | 1998 |
publishDateSearch | 1998 |
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publisher | IAEA |
record_format | marc |
series | International Atomic Energy Agency: Technical reports series |
series2 | International Atomic Energy Agency: Technical reports series |
spelling | Review of fuel failures in water cooled reactors International Atomic Energy Agency STI DOC 010 388 Vienna IAEA 1998 167 S. Ill., graph. Darst. txt rdacontent n rdamedia nc rdacarrier International Atomic Energy Agency: Technical reports series 388 Combustibles nucleares embne Nuclear fuel elements System failures (Engineering) Water cooled reactors Wassergekühlter Reaktor (DE-588)4126461-7 gnd rswk-swf Brennelement (DE-588)4136903-8 gnd rswk-swf Versagen (DE-588)4258790-6 gnd rswk-swf (DE-588)1071861417 Konferenzschrift gnd-content Wassergekühlter Reaktor (DE-588)4126461-7 s Brennelement (DE-588)4136903-8 s Versagen (DE-588)4258790-6 s DE-604 International Atomic Energy Agency: Technical reports series 388 (DE-604)BV000022590 388 Digitalisierung TU Muenchen application/pdf http://bvbr.bib-bvb.de:8991/F?func=service&doc_library=BVB01&local_base=BVB01&doc_number=008238762&sequence=000002&line_number=0001&func_code=DB_RECORDS&service_type=MEDIA Inhaltsverzeichnis |
spellingShingle | Review of fuel failures in water cooled reactors International Atomic Energy Agency: Technical reports series Combustibles nucleares embne Nuclear fuel elements System failures (Engineering) Water cooled reactors Wassergekühlter Reaktor (DE-588)4126461-7 gnd Brennelement (DE-588)4136903-8 gnd Versagen (DE-588)4258790-6 gnd |
subject_GND | (DE-588)4126461-7 (DE-588)4136903-8 (DE-588)4258790-6 (DE-588)1071861417 |
title | Review of fuel failures in water cooled reactors |
title_alt | STI DOC 010 388 |
title_auth | Review of fuel failures in water cooled reactors |
title_exact_search | Review of fuel failures in water cooled reactors |
title_full | Review of fuel failures in water cooled reactors International Atomic Energy Agency |
title_fullStr | Review of fuel failures in water cooled reactors International Atomic Energy Agency |
title_full_unstemmed | Review of fuel failures in water cooled reactors International Atomic Energy Agency |
title_short | Review of fuel failures in water cooled reactors |
title_sort | review of fuel failures in water cooled reactors |
topic | Combustibles nucleares embne Nuclear fuel elements System failures (Engineering) Water cooled reactors Wassergekühlter Reaktor (DE-588)4126461-7 gnd Brennelement (DE-588)4136903-8 gnd Versagen (DE-588)4258790-6 gnd |
topic_facet | Combustibles nucleares Nuclear fuel elements System failures (Engineering) Water cooled reactors Wassergekühlter Reaktor Brennelement Versagen Konferenzschrift |
url | http://bvbr.bib-bvb.de:8991/F?func=service&doc_library=BVB01&local_base=BVB01&doc_number=008238762&sequence=000002&line_number=0001&func_code=DB_RECORDS&service_type=MEDIA |
volume_link | (DE-604)BV000022590 |