| Description |
1 online resource (175 pages) : illustrations (some color) |
| Series |
IAEA nuclear energy series, 1995-7807 ; no. NF-T-2.1 |
|
IAEA nuclear energy series ; no. NF-T-2.1.
|
| Contents |
Cover -- Foreword -- Contents -- Summary -- 1. Introduction -- 1.1.Background -- 1.2.Objective -- 1.3.Scope -- 1.4.Structure -- References To Section 1 -- 2. Evolution Of Fuel Operating Environmentand Fuel Design Changes -- 2.1.Evolution Of Fuel Operating Environment -- 2.2.Fuel Design Evolution -- 2.3.Fuel Types In Operation -- References To Section 2 -- 3. World Overview Of Fuel Failures From 1994 To 2006 -- 3.1.Introduction -- 3.2.Coolant Activity Levels -- 3.3.Methodology Of Fuel Failure Rate Evaluation -- 3.4.Collection And Treatment Of Fuel Failure Data -- 3.5.Evaluation Of Pwr Fuel â#x80;#x98;Leakersâ#x80;#x99; -- 3.6.Evaluation Of Bwr Fuel â#x80;#x98;Leakersâ#x80;#x99; -- 3.7.Evaluation Of Wwer Fuel â#x80;#x98;Leakersâ#x80;#x99; -- 3.8.Evaluation Of Fuel â#x80;#x98;Leakersâ#x80;#x99; In Candus/Phwrs -- 3.9.Multiple Failure Incidents/Defect Excursions -- 3.10.Fuel Rod Failure Rates And Fuel Failure Causes Between 1987â#x80;#x93;2006 -- 3.11.Concluding Remarks -- References To Section 3 -- 4. Detection, Examination And Analysis Of Fuel Failures -- 4.1.Introduction -- 4.2.Evaluation Of Coolant Activity -- 4.3.Localization Of Fuel Failures -- 4.4.Fuel Examination -- 4.5.Fuel Failure Analysis -- References To Section 4 -- 5. Mechanisms And Root Causes Of Fuel Failure -- 5.1.Introduction -- 5.2.Grid To Rod Fretting -- 5.3.Fretting Due To Debris -- 5.4.Corrosion -- 5.5.Pelletâ#x80;#x93;Cladding Interaction -- 5.6.Manufacturing Defects -- 5.7.Cross-Flow/Baffle Jetting -- 5.8.Primary Hydriding -- 5.9.Delayed Hydride Cracking (Dhc) -- References To Section 5 -- 6. Fuel Structural Damage And Other Fuel Assembly Issues -- 6.1.Introduction -- 6.2.Assembly Bow -- 6.3.Mechanical Damage During Handling -- 6.4.Crud And Axial Offset Anomalies (Aoa) -- 6.5.Other Miscellaneous Damage -- References To Section 6 -- 7. Secondary Fuel Failures -- 7.1.Background -- 7.2.Observations From Experience -- 7.3.Degradation Characteristics |
|
7.4.Mechanisms -- 7.5.Circumferential Fractures -- References To Section 7 -- 8. Fuel Failure Prevention And Management In Plant Operation -- 8.1.Existing Operating Limits And Recommended Practices -- 8.2.Improvement Of Quality During Manufacturing -- References To Section 8 -- 9. Conclusions -- Abbreviations -- Contributors To Drafting And Review |
| Summary |
This publication responds to the growing awareness of a need for open discussion and concerted actions to improve nuclear fuel reliability. It contains unique worldwide statistics on fuel failure rates, covering about 96% of water cooled reactor fuels. This gives the most representative picture of fuel reliability available in the open literature and presents a number of valuable conclusions. The publication also describes modern methods of detection and examination of fuel failures, analyzes their mechanisms and root causes, and recommends failure prevention and mitigation measures. These data and information are important elements for closing the circle of the fuel quality management system through providing feedback information about fuel performance--Publisher's description |
| Analysis |
Nuclear power plants Management |
|
Nuclear power plants Safety regulations |
| Notes |
"STI/PUB/1445"--PDF t.p. verso |
|
"The IAEA officers responsible for this publication was V. Inozemtsev of the Division of Nuclear Fuel Cycle and Waste Technology"--PDF Foreword page |
| Bibliography |
Includes bibliographical references |
| Notes |
System requirements: Adobe Acrobat Reader for Windows |
|
Print version record |
| Subject |
Water cooled reactors -- Fuel systems -- Reliability -- Statistics
|
|
Nuclear fuel elements.
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|
System failures (Engineering)
|
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Nuclear fuel elements
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System failures (Engineering)
|
| Genre/Form |
Statistics
|
| Form |
Electronic book
|
| Author |
Inozemtsev, Victor
|
|
International Atomic Energy Agency.
|
| ISBN |
9789201026101 |
|
9201026102 |
|
