ACI 349.3R 02 2002
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349.3R-02: Evaluation of Existing Nuclear Safety Related Concrete Structures(Reapp 2010)
| Published By | Publication Date | Number of Pages |
| ACI | 2002 | 20 |
This document is available in PDF format only This report recommends guidelines for the evaluation of existing nuclear safety-related concrete structures. The purpose of this report is to provide the plant owner and engineering staff with an appropriate procedure and background for examining the performance of facility structures and taking appropriate actions based on observed conditions. Methods of examination, including visual inspection and testing techniques, and their recommended applications are cited. Guidance related to acceptance criteria for various forms of degradation is also provided. Keywords: corrosion; cracking; degradation; inspection; load test; nuclear power plant; reinforced concrete; reinforcement; reinforcing steels; safety; serviceability; structural design; test.
PDF Catalog
| PDF Pages | PDF Title |
|---|---|
| 1 | CONTENTS |
| 2 | CHAPTER 1— INTRODUCTION CHAPTER 2— GENERAL METHODOLOGY |
| 3 | CHAPTER 3— EVALUATION PROCEDURE 3.1— Scope 3.2—Selective evaluation 3.3—Periodic evaluation |
| 4 | 3.4—Evaluation procedure development 3.5—Evaluation techniques 3.5.1 Visual inspection |
| 5 | 3.5.2 Nondestructive evaluation |
| 6 | 3.5.3 Invasive testing 3.5.4 Analytical methods |
| 7 | 3.5.5 Summary CHAPTER 4— DEGRADATION MECHANISMS 4.1— General |
| 8 | 4.2—Concrete degradation 4.2.1 Abrasion and erosion |
| 9 | 4.2.2 Chemical attack 4.2.3 Thermal exposure 4.2.4 Fatigue 4.2.5 Cement-aggregate reactions 4.2.6 Freezing and thawing |
| 10 | 4.2.7 Irradiation 4.2.8 Leaching 4.2.9 Volume changes 4.2.10 External loads 4.2.11 Fire damage |
| 11 | 4.2.12 Steam impingement 4.2.13 Settlement 4.2.14 Tendon grease leakage effects 4.3—Steel reinforcement and structural steel degradation 4.3.1 Corrosion 4.3.2 Fatigue |
| 12 | 4.3.3 Thermal effects 4.3.4 Irradiation 4.4—Prestressing steel degradation 4.4.1 Corrosion 4.4.2 Stress corrosion cracking and hydrogen embrittlement 4.4.3 Loss of prestress |
| 13 | 4.4.4 Thermal effects and irradiation CHAPTER 5— EVALUATION CRITERIA 5.1—Acceptance without further evaluation 5.1.1 Concrete surfaces |
| 14 | 5.1.2 Concrete surfaces lined with metal or plastic |
| 15 | 5.1.3 Areas around embedments in concrete 5.1.4 Joints, coatings, and nonstructural components 5.1.5 Prestressing-steel systems 5.2—Acceptance after review 5.2.1 Concrete surfaces 5.2.2 Concrete surfaces lined by metallic or plastic liners 5.2.3 Areas around embedments in concrete 5.2.4 Joints, coatings, and nonstructural components 5.2.5 Prestressing-steel systems |
| 16 | 5.3—Conditions requiring further evaluation CHAPTER 6— EVALUATION FREQUENCY CHAPTER 7— QUALIFICATION S OF EVALUATION TEAM |
| 17 | CHAPTER 8— REPAIR |
| 18 | CHAPTER 9— REFERENCES 9.1— Referenced standards and reports |
| 19 | 9.2—Cited references |
