Proceedings of the 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors (eBook)

The Minerals, Metals & Materials Society (TMS) is a member-driven international professional society dedicated to fostering the exchange of learning and ideas across the entire range of materials science and engineering, from minerals processing and primary metals production, to basic research and the advanced applications of materials. Included among its nearly 13,000 professional and student members are metallurgical and materials engineers, scientists, researchers, educators, and administrators from more than 70 countries on six continents.

Preface 5
In Memoriam 7
Roger Washburne Staehle (February 4, 1934–January 16, 2017) 7
Contents 10
About the Editors/Organizers 27
Organizing Committee for Environmental Degradation Conferences 30
Session Chairs and Co-chairs 32
PWR Nickel SCC—SCC 35
1 Scoring Process for Evaluating Laboratory PWSCC Crack Growth Rate Data of Thick-Wall Alloy 690 Wrought Material and Alloy 52, 152, and variant Weld Material 36
Abstract 36
Introduction 37
Data Compilation 37
Scoring Process 38
Scoring Approach 39
Scoring Criteria 40
Testing Environment 40
Loading Conditions 41
Test Segment Duration and Growth Increment 41
Single-Condition Tests 41
Fatigue Precracking and Transitioning to SCC 42
Post-Test Correction 42
Additional Criteria 43
Scoring Results 43
Conclusions 46
Acknowledgements 46
References 47
2 Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components 48
Abstract 48
Introduction 48
Base Metal Effects 50
Crack Growth Orientation Versus Product Form 52
Measurement of Welding Residual Strains in Prototypic Welds 54
Weld Metal Effects and HAZ 56
Cold Work Versus Warm Work 57
Summary and Conclusions 58
Acknowledgements 58
References 58
3 SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones in PWR Water 59
Abstract 59
Introduction 59
Experimental Procedures 62
Results on Alloy 152/52/52i Weld Metals 65
Weld Repairs 69
Weld With Refuse Passes 69
Welds With Ductility Dip Cracking (DDC) 69
Welds Dilution Zones 73
Discussion 74
Conclusions 82
References 82
4 NRC Perspectives on Primary Water Stress Corrosion Cracking of High-Chromium, Nickel-Based Alloys 86
Abstract 86
Introduction 87
Interpretation of PPU Data 88
Treatment of Cold Worked Material 90
Weld Interface and Dilution Zone (DZ) Testing 91
Stress Intensity Factor and Temperature Dependencies 92
Heat-to-Heat Variations 93
Summary 94
References 95
5 Stress Corrosion Cracking of Alloy 52/152 Weldments Near Dissimilar Metal Weld Interfaces 97
Abstract 97
Introduction 97
Experimental Methods 101
Results 102
Alloy 152-LAS Specimen N152-LAS-11 102
Alloy 152-LAS Specimen N152-LAS-1 106
Alloy 152-LAS Specimen N152-LAS-22 108
Alloy 52M-182 Specimen WOL-ST-2 109
Discussion 113
Conclusions 114
Acknowledgements 114
References 114
6 Stress Corrosion Crack Growth Rate Testing of Composite Material Specimens 116
Abstract 116
Introduction 116
Experimental Methods 117
Results and Discussion 117
Specimen Analytical Characterization Results 120
SCC Growth Rates (SCCGRs) 128
Conclusions 131
References 132
7 Investigation of Hydrogen Behavior in Relation to the PWSCC Mechanism in Alloy TT690 133
Abstract 133
Introduction 133
Experimental 135
Specimens and Basic Test Conditions 135
Cavity Formation at Crack Tips 135
Influence of Hydrogen Gas 136
Influence of Dynamic Strain Aging 137
Nickel Plating PWSCC Propagation Test 137
Results 137
Cavity Formation at Crack Tips 137
Influence of Hydrogen Gas 139
Influence of Dynamic Strain Aging 140
Nickel Plating SCC Propagation Test 141
Discussion 143
Conclusions 145
References 146
PWR Nickel SCC—Initiation 147
8 Crack Initiation of Alloy 600 in PWR Water 148
Abstract 148
Introduction 148
Experimental Procedures 149
Results and Discussion—Initiation Data 152
Results and Discussion—SCC Growth Rate Data 158
Conclusions 161
References 162
9 SCC Initiation Behavior of Alloy 182 in PWR Primary Water 163
Abstract 163
Introduction 163
Experimental Procedures 164
Materials and Specimens 164
Test Methods 166
Microstructural Characterizations 168
Results and Discussion 169
SCC Initiation Measurements 169
Microstructural Characterizations of 15% CF Alloy 182 Initiation Specimens 171
Pre-existing Defects 171
SCC Initiation Microstructures 174
Conclusion 185
Acknowledgements 186
References 186
10 Multiple Cracks Interactions in Stress Corrosion Cracking: In Situ Observation by Digital Image Correlation and Phase Field Modeling 187
Abstract 187
Introduction 188
Experimental Procedures 190
Experimental Results and Discussion 191
2D Analysis of the Stress Corrosion Cracks Colony 191
Phase Field Modeling from 2D Experimental Data 193
DVC Analysis of the Stress Corrosion Cracks Colony 193
Validation of 2D Measurements 194
Shape of the Intergranular Stress Corrosion Cracks 195
Conclusions 198
Acknowledgements 198
References 198
11 Stress Corrosion Cracking Initiation of Alloy 82 in Hydrogenated Steam 201
Abstract 201
Introduction 202
Materials and Methods 203
Material 203
EPMA 207
SIMS 207
Initiation Tests 207
Results 208
Crack Initiation Tests 208
Correlation Between Microstructure and Crack Initiation 210
Chemical Heterogeneities in the Welds 212
Conclusions 214
Acknowledgements 214
References 214
12 Application of Ultra-High Pressure Cavitation Peening on Reactor Vessel Head Penetration, BMN and Primary Nozzles 216
Abstract 216
Introduction 217
Laboratory Tests 218
Qualification Process 221
Regulatory Background and Roadmap 223
Application to RPV Head Penetration 224
Conclusion 225
References 226
13 The Effect of Surface Condition on Primary Water Stress Corrosion Cracking Initiation of Alloy 600 227
Abstract 227
Introduction 227
Experimental Methods 228
Materials and Specimens 228
Machining Parameter Trial 230
PWSCC Initiation Testing 230
Results 232
Surface Characterisation 232
PWSCC Initiation Testing Results 233
Discussion 236
Effect of Surface Condition on PWSCC Initiation Susceptibility 236
Effect of Machining Parameters on Surface Condition 238
Conclusions 239
References 240
14 Microstructural Effects on SCC Initiation in PWR Primary Water for Cold-Worked Alloy 600 241
Abstract 241
Introduction 241
Experimental Procedures 242
Materials and Specimens 242
Test Methods 242
Microstructural Characterizations 245
Results and Discussion 245
Conclusion 252
Acknowledgements 253
References 253
PWR Nickel SCC—Aging Effects 254
15 A Kinetic Study of Order-Disorder Transition in Ni–Cr Based Alloys 255
Abstract 255
Introduction 255
Background 256
Materials and Method 258
Results 261
Ordering Kinetics Followed by Hardness 261
Ordering Kinetics Followed by ThermoElectric Power 262
Ordering Kinetics Followed by Transmission Electron Microscope 263
Extrapolation to Industrial Alloys 265
Discussion 266
Conclusions 269
Acknowledgements 269
References 270
16 The Role of Stoichiometry on Ordering Phase Transformations in Ni–Cr Alloys for Nuclear Applications 272
Abstract 272
Introduction 273
Experimental Methods 274
Results and Discussion 275
Transmission Electron Microscopy 275
Atom Probe Tomography 277
Micro-hardness 277
Conclusions 279
Acknowledgements 280
References 280
17 The Effect of Hardening via Long Range Order on the SCC and LTCP Susceptibility of a Nickel-30Chromium Binary Alloy 281
Abstract 281
Background 282
Experimental Procedure 283
Results 286
Material Properties 286
EPD Results of SCC Testing 286
Destructive Examination of SCC Testing 286
LTCP Test Results 287
Discussion 292
Key Functionalities of SCC 292
LTCP Susceptibility of Ordered Ni-30.7Cr wt% Model Alloy 297
Conclusions 297
Acknowledgements 298
References 298
18 PWSCC Initiation of Alloy 600: Effect of Long-Term Thermal Aging and Triaxial Stress 300
Abstract 300
Introduction 301
Experiment 302
Material 302
Experimental Procedure 302
Results and Discussions 305
Microstructure and Mechanical Properties 305
PWSCC Test 306
Conclusions 309
Acknowledgements 310
References 310
19 Stress Corrosion Cracking Behavior of Alloy 718 Subjected to Various Thermal Mechanical Treatments in Primary Water 312
Abstract 312
Introduction 312
Experimental 313
Materials and Samples Design 313
Mechanical Properties Test Conditions 315
CERT Test and Crack Characterization 315
Results 316
Microstructure and Mechanical Properties of Alloy 718 316
Cracking Behavior in PWR Primary Water 317
Discussion 319
Microstructure Evolution with Chemical Composition 319
Effect of Microstructure on SCC Susceptibility 320
Conclusion 322
Acknowledgements 323
References 323
20 Time- and Fluence-to-fracture Studies of Alloy 718 in Reactor 325
Abstract 325
Introduction 325
Experimental 326
Results and Discussion 327
Discussion 336
Conclusions 337
Acknowledgements 337
References 337
21 Development of Short-Range Order and Intergranular Carbide Precipitation in Alloy 690 TT upon Thermal Ageing 339
Abstract 339
Introduction 340
Experimental Methods 341
Results 342
Grain Size and Grain Boundary Evolution 342
Nature of Intergranular Precipitation 343
Hardness and Lattice Parameter Measurements 344
Consequences of Thermal Ageing on Strain Localization 347
Discussion 347
Conclusions 349
Acknowledgements 350
References 350
PWR Nickel SCC—Alloy 600 Mechanistic 353
22 Diffusion Processes as Possible Mechanisms for Cr Depletion at SCC Crack Tip 354
Abstract 354
Introduction 355
Experimental 356
Materials 356
DIGM: Thermal Treatments and Microstructural Characterizations 357
Diffusion During Creep 357
Results 359
Diffusion-Induced Grain Boundary Migration 359
As-Received State 359
After Annealing Under Vacuum 360
After Oxidation in Primary Water 363
Diffusion-Plasticity Coupling 364
Creep Tests Results 365
Effect of Ongoing Plasticity on the Diffusion Coefficients 366
Modeling the Cr Depletion 369
Description of the Wagner’s Model and Used Hypothesis 370
Application to the DIGM Mechanism 371
Application to the Plasticity-Enhanced Diffusion Mechanism 371
Conclusions 372
Acknowledgements 372
References 373
23 Role of Grain Boundary Cr5B3 Precipitates on Intergranular Attack in Alloy 600 375
Abstract 375
Introduction 375
Materials and Methods 376
Results 377
Overview of TT Microstructures and IGA Responses 377
Characterization of Pristine Grain Boundaries with Cr5B3 Precipitates 379
Characterization of Corroded Grain Boundaries with Cr5B3 Precipitates 380
Comparison with Corroded Grain Boundary Containing Cr-Carbide Precipitates 385
Discussion 386
Conclusion 388
Acknowledgements 388
References 388
24 Advanced Characterization of Oxidation Processes and Grain Boundary Migration in Ni Alloys Exposed to 480 °C Hydrogenated Steam 391
Abstract 391
Introduction 392
Experimental Methods 394
Materials 394
Experimental Conditions and Procedures 395
Surface Science and Electron Microscopy Characterization 395
Scanning Electron Microscopy (SEM) 395
Scanning Transmission Electron Microscopy (STEM) 395
Atom Probe Tomography (APT) 396
Focused Ion Beam (FIB) Serial Sectioning 396
Time of Flight Secondary Ion Mass Spectroscopy (ToF-SIMS) 397
Results and Discussion 397
Diffusion-Induced Grain Boundary Migration (DIGM) in Alloy 600 397
Initial Intergranular Oxidation Processes in Alloy 600 403
Internal Oxidation of Alloy 690 406
Conclusions 410
References 411
25 Exploring Nanoscale Precursor Reactions in Alloy 600 in H2/N2–H2O Vapor Using In Situ Analytical Transmission Electron Microscopy 415
Abstract 415
Introduction 415
Materials and Methods 416
Results 418
Baseline Experiments 418
In Situ Exposure in H2/N2–H2O Vapor at 400 °C 419
Post-test Characterisation of the in Situ Specimen 421
Discussion 422
Conclusions 422
Acknowledgements 422
References 423
26 Electrochemical and Microstructural Characterization of Alloy 600 in Low Pressure H2-Steam 424
Abstract 424
Introduction 424
Experimental Procedures 426
H2-Steam Environment 426
Electrochemical Measurement of the Ni/NiO Transition and Oxidation Studies of Alloy 600 427
Sample Preparation 428
Microstructural Examinations 428
Results and Discussion 429
Electrochemical Measurement of the Ni/NiO Transition and Alloy 600 Oxidation Studies 429
Alloy 600 431
Microstructural Characterization After H2-Steam Exposure 431
Conclusions 435
Acknowledgements 436
References 436
27 Effect of Dissolved Hydrogen on the Crack Growth Rate and Oxide Film Formation at the Crack Tip of Alloy 600 Exposed to Simulated PWR Primary Water 438
Abstract 438
Introduction 438
Experimental 439
CGR Measurement 439
TEM Lamella Liftout with FIB/SEM 440
TEM Instrumentation 442
Results and Discussion 442
CGR Versus DH 442
Oxide Film Microstructures Versus DH 445
At DH 5 cc H2/Kg H2O 445
At DH 16 cc H2/Kg H2O 446
At DH 45 cc H2/Kg H2O 448
At DH 75 cc H2/Kg H2O 449
Summary 451
Acknowledgements 451
References 451
28 A Mechanistic Study of the Effect of Temperature on Crack Propagation in Alloy 600 Under PWR Primary Water Conditions 453
Abstract 453
Introduction 454
Experimental 455
Material and SCC Test 455
Methodology 456
Site-Specific Sample Preparation with FIB 456
ATEM Analysis 456
TKD Analysis 456
Results 457
ATEM Characterization 458
TKD Characterization 459
Discussion 461
The Influence of Temperature on Thermally Activated Intergranular Diffusion 463
The Influence of Temperature on the Formation of Intergranular Protective Cr-Rich Oxide 464
The Influence of Temperature on the Intensity of the Deformation Around the Crack Tip 465
The Dependence of Temperature on CGR of SCC 466
Conclusions 466
Acknowledgements 467
References 467
PWR Nickel SCC—Alloy 690 Mechanistic 469
29 Grain Boundary Damage Evolution and SCC Initiation of Cold-Worked Alloy 690 in Simulated PWR Primary Water 470
Abstract 470
Introduction 470
Experimental Procedures 472
Materials, Specimens and Test Method 472
Microstructural Characterizations 477
Scanning Electron Microscopy and Focused Ion Beam Examinations 477
Quantification of GB Cavity Distribution 478
Results 480
DCPD Measurements 480
Gauge Surface Examination of GB Damage 481
Precursor Damage and Crack Morphology on the Surface of the Polished Specimens 481
FIB Examination on Selected Polished Specimens 484
Cross-Section Examination of GB Damage 487
GB Cavity Morphology in CLT Specimen Cross-Sections 487
GB Cavity Quantification 488
Discussion 491
Effect of Cold Work and Applied Stress on GB Cavity Evolution 493
Effect of Starting Microstructure on GB Cavity Evolution 493
Conclusion 495
Acknowledgements 495
References 495
30 PWSCC Susceptibility of Alloy 690, 52 and 152 497
Abstract 497
Introduction 498
Experimental Procedures 499
SCC Initiation Test Using Mechanical Plug Mock-up 499
SCC Initiation Test by Constant Load Specimens 500
SCC Propagation Test 501
Results and Discussion 503
SCC Test for Mechanical Plug 503
SCC Initiation Test by Constant Load Specimens 508
SCC Propagation Test 509
Conclusions 510
Acknowledgements 511
References 511
31 Relationship Among Dislocation Density, Local Strain Distribution, and PWSCC Susceptibility of Alloy 690 513
Abstract 513
Introduction 513
Experimental Procedures 514
Results and Discussion 515
Conclusions 517
Acknowledgements 518
References 518
32 Morphology Evolution of Grain Boundary Carbides Precipitated Near Triple Junctions in Highly Twinned Alloy 690 520
Abstract 520
Introduction 520
Experimental Procedures 521
Results and Discussion 522
Conclusion 526
Acknowledgements 527
References 527
33 A Mechanistic Study of Stress Corrosion Crack Propagation in Heavily Cold Worked TT Alloy 690 Exposed to Simulated PWR Primary Water 529
Abstract 529
Introduction 530
Experimental Procedures 531
Test Materials and Test Specimens 531
SCCGR Measurement Test and SCC Initiation Test Conditions 533
Microstructural Analyses 536
Results and Discussion 536
Effect of M23C6 Primary GB Carbides on SCCGR 536
Results of SCC Initiation Tests 538
Effect of Ni Content on SCCGR 538
Cavities Near GB Carbides 538
Conclusions 543
Acknowledgements 543
References 544
34 Microstructural Study on the Stress Corrosion Cracking of Alloy 690 in Simulated Pressurized Water Reactor Primary Environment 545
Abstract 545
Introduction 546
Experiment 546
Results 547
Discussion 551
Grain Boundary Migration 551
Intergranular Oxidation 552
Conclusions 553
Acknowledgements 553
References 554
Irradiation Damage—Stainless Steel 556
35 Effect of Strain Rate and High Temperature Water on Deformation Structure of VVER Neutron Irradiated Core Internals Steel 557
Abstract 557
Introduction 557
Experimental 560
Material 560
Specimen 560
Results 563
Radiation Damage 563
Effect of Strain Rate and Temperature 565
Effect of Water Environment 567
Discussion 568
Conclusions 570
Acknowledgements 570
References 570
36 Radiation-Induced Precipitates in a Self-ion Irradiated Cold-Worked 316 Austenitic Stainless Steel Used for PWR Baffle-Bolts 572
Abstract 572
Introduction 573
Experimental 575
Material 575
Self-ion Irradiation 576
Post-irradiation TEM Sample Preparation and Microanalysis 577
Results and Discussion 578
Conclusions 585
Acknowledgements 586
References 586
37 In Situ and Ex Situ Observations of the Influence of Twin Boundaries on Heavy Ion Irradiation Damage Effects in 316L Austenitic Stainless Steels 588
Introduction 588
Experimental Methods 589
Materials 589
In Situ Irradiation 590
Ex Situ Characterization 590
Results 590
In Situ Observations 590
Absorption of Defects by Twin Boundaries 590
Lifetime of Mobile Defects 591
Ex Situ STEM Observations 592
Annealing Twin Boundaries 592
Deformation Twin Boundaries 593
Conclusions and Future Work 595
References 598
38 In Situ Microtensile Testing for Ion Beam Irradiated Materials 599
Abstract 599
Introduction 600
Sample Irradiation 601
Micropillar and Microtensile Fabrication 601
Comparison Between Microtensile and Microcompression Testing 603
Load Drop Analysis 605
Interfacial Tensile Testing of an Alloy 600 606
Conclusion 608
Acknowledgements 609
References 609
39 Development of High Irradiation Resistant and Corrosion Resistant Oxide Dispersion Strengthened Austenitic Stainless Steels 610
Abstract 610
Introduction 610
Experimental Method 612
Conclusions 618
References 620
40 Spherical Nanoindentation Stress-Strain Analysis of Ion-Irradiated Tungsten 621
Abstract 621
Introduction 622
Experimental Details 623
Spherical Indentation Stress-Strain (ISS) Curves 625
Results and Discussion 627
Indentation Stress-Strain Response of Annealed Versus He-Irradiated Tungsten 627
Effect of Ion-Species on the Indentation Stress-Strain Response: Annealed, He, W Versus He+W Irradiation 633
Orientation Effects on the Indentation Stress-Strain Response of the Irradiated Material 633
Conclusion 636
Acknowledgements 636
References 636
Irradiation Damage—Swelling 640
41 Formation of He Bubbles by Repair-Welding in Neutron-Irradiated Stainless Steels Containing Surface Cold-Worked Layer 641
Abstract 641
Introduction 641
Experimental Procedure 642
Test Specimen Material 642
Bead-on-Plate Welding Test 643
Test Results 643
Discussion 649
Conclusions 650
Acknowledgements 651
References 651
42 Predictions and Measurements of Helium and Hydrogen in PWR Structural Components Following Neutron Irradiation and Subsequent Charged Particle Bombardment 653
Abstract 653
Introduction 653
Sources of Helium and Hydrogen in the Flux Thimble Tubes 656
Recommendations on Gas Co-injection Rates for Ion Irradiations 666
Conclusions 668
Acknowledgements 669
References 669
43 Emulating Neutron-Induced Void Swelling in Stainless Steels Using Ion Irradiation 671
Abstract 671
Introduction 671
Materials and Experiments 674
Results and Discussion 676
Summary 679
Acknowledgements 680
References 680
44 Carbon Contamination, Its Consequences and Its Mitigation in Ion-Simulation of Neutron-Induced Swelling of Structural Metals 683
Abstract 683
Introduction 683
Experimental Procedure 685
Results: Carbon Enrichment 686
Carbon Contamination Mechanism 687
A Technique of Multiple Beam Bending Developed to Remove Carbon from the Beam 688
Demonstration of the Effectiveness of the Technique 690
Discussion 690
Acknowledgements 693
References 693
45 Void Swelling Screening Criteria for Stainless Steels in PWR Systems 696
Abstract 696
Introduction 697
Past Void Swelling Studies of Austenitic Stainless Steels 697
Void Swelling Data from Various Programs 700
Void Swelling Data from PWR Reactor Vessel Internals Components 701
Recent Cluster Dynamics Modeling 701
Factors Affecting Void Swelling 704
Void Swelling Screening Criteria Summary 705
Conclusions 707
References 707
46 Theoretical Study of Swelling of Structural Materials in Light Water Reactors at High Fluencies 710
Abstract 710
Introduction 710
Computational Model 714
Calculation Results 716
Gas-Assisted Void Nucleation 716
Swelling Accumulation at LWR Conditions 720
Conclusions 722
Acknowledgements 723
References 723
Irradiation Damage—Nickel Based and Low Alloy 725
47 High Resolution Transmission Electron Microscopy of Irradiation Damage in Inconel X-750 726
Abstract 726
Introduction 726
Experimental 728
Results 729
Stability of Secondary y' Precipitates 729
Radiation Induced Defects 730
Helium Bubble Characterization 732
Conclusions 738
Acknowledgements and Collaborating Partners 739
References 739
48 In Situ SEM Push-to-Pull Micro-tensile Testing of Ex-service Inconel X-750 741
Abstract 741
Introduction 742
Experimental Method 744
Material 744
In Service Damage and Hydrogen and Helium Production 745
Sample Preparation 747
Electron Backscattered Diffraction (EBSD) Pre-analysis 747
In Situ Push-to-Pull Micro-tensile Testing 748
Results 749
Discussion 751
Conclusions 754
Acknowledgements 754
References 754
49 Microstructural Characterization of Proton-Irradiated 316 Stainless Steels by Transmission Electron Microscopy and Atom Probe Tomography 756
Abstract 756
Introduction 756
Experimental 758
Materials and Proton Irradiation 758
Sample Preparation of the Irradiated Materials 758
Microstructural Analysis 759
Results and Discussions 760
Microstructure of the Non-irradiated Material 760
Microstructure of the Proton-Irradiated Materials 761
APT Analysis of the Proton-Irradiated Materials 763
Effect of Irradiation on the Mechanical Properties and IASCC 765
Chemical Polishing Effects on the FIM TEM Specimens 766
Conclusions 767
Acknowledgements 768
References 768
PWR Stainless Steel SCC and Fatigue—SCC 770
50 Microstructural Effects on Stress Corrosion Initiation in Austenitic Stainless Steel in PWR Environments 771
Abstract 771
Introduction 772
Materials 773
Experimental 775
Results 776
Heat A 777
Heat B 780
Discussion 784
Conclusions 786
References 787
51 Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water 789
Abstract 789
Introduction 790
Experimental Details 791
Material 791
Sample Geometry and Surface Preparation 791
SCC Testing 792
Microstructural Characterization 792
Results 793
Baseline Materials Characterization 793
Effect of Inclusions on Oxidation and Cracking 793
Effect of Strain and Strain Rate on the SCC Initiation: Tapered Specimens 795
Effect of Machining 798
Effect of Carbon Contamination on Oxidation and Crack Initiation 800
Discussion 801
Conclusions 803
Acknowledgements 804
References 804
52 SCC Initiation in the Machined Austenitic Stainless Steel 316L in Simulated PWR Primary Water 807
Abstract 807
Introduction 807
Material and Experiment 809
Results and Discussion 810
Pre-test Characterization 810
Surface Roughness, Residual Stresses, and Machining Marks Orientation 810
Cross Sectional Microstructure of the Machined Surfaces 811
Post-test Microstructural Characterization 812
Plan-View Characterization of Specimens 812
Characterisation of Cross-Section Specimens 814
Discussion 818
Influence of the Machining-Induced Deformation Layer on SCC Initiation 818
The Influences of the Residual Stress and Orientation of the Machining Marks 820
Conclusions 821
Acknowledgements 821
References 821
53 High-Resolution Characterisation of Austenitic Stainless Steel in PWR Environments: Effect of Strain and Surface Finish on Crack Initiation and Propagation 824
Abstract 824
Introduction 825
Materials and Methods 825
Results 828
Baseline Characterisation 828
Unstressed Coupon Exposure Tests 828
C3R2C1 831
SSRT-T2 831
SSRT-T1 835
Discussion 836
Surface Finish Effects 836
Strain Effects 839
Local Strain 840
Conclusions 841
Acknowledgements 841
References 841
54 SCC of Austenitic Stainless Steels Under Off-Normal Water Chemistry and Surface Conditions 843
Abstract 843
Introduction 843
Materials of Interest 845
Test Specimens 845
Off-Normal Surface Conditions 846
Reference Surface Conditions 848
Specimens Forming 849
Specimens Loading Characterizations 849
Test Apparatus 852
Results 852
Conclusion 856
References 857
55 SCC of Austenitic Stainless Steels Under Off-Normal Water Chemistry and Surface Conditions 858
Abstract 858
Introduction 858
Test Material 861
Testing 862
Testing in Hydrogenated (Nominal) PWR Primary Environment 862
Testing in Oxygenated in PWR Primary Conditions 862
Testing in Transients PWR Primary Environment 863
Test Results 864
Testing in Hydrogenated (Nominal) PWR Primary Conditions 865
Testing in Oxygenated PWR Primary Conditions 865
Testing in Transients PWR Primary Environment 870
Conclusion 871
References 873
56 The Effect of Microchemistry on the Crack Response of Lightly Cold Worked Dual Certified Type 304/304L Stainless Steel After Sensitizing Heat Treatment 874
Abstract 874
Introduction 874
Experimental 875
Results 876
Crack Growth 876
Grain Boundary and Interface Chemistry 879
Discussion 881
Microchemical Influence on Stress Corrosion Cracking 881
Dual Certified Type 304/304L SS Compared to Type 304 SS 883
Conclusions 883
Acknowledgements 883
References 884
PWR Stainless Steel SCC and Fatigue—Fatigue 885
57 The Effect of Load Ratio on the Fatigue Crack Growth Rate of Type 304 Stainless Steels in Air and High Temperature Deaerated Water at 482 °F 886
Abstract 886
Introduction 886
Experimental Procedures 888
Materials 888
Air Testing 889
Autoclave Testing 890
Autoclave Configuration, Load Control, and Crack Measurement 890
Environment Specification and Control 891
Test-Specific Loading/Execution 891
Post Test Analysis 891
Results 892
Air Results 892
High Temperature Water Results 893
Discussion 899
Conclusions 900
Acknowledgements 901
References 901
58 Electrical Potential Drop Observations of Fatigue Crack Closure 903
Abstract 903
Background 903
EPD Closure Measurement Technique 904
Observations of Closure 907
High and Low Sulfur Stainless Steel Compact Tension Specimens 907
Overload Experiment on Surface Crack Specimen 909
Effect of R-Ratio on Crack Closure in Surface Cracked Specimens 910
Discussion of EPD Closure 911
Conclusions 914
Acknowledgements 915
References 915
59 The Effect of Environment and Material Chemistry on Single-Effects Creep Testing of Austenitic Stainless Steels 916
Abstract 916
Introduction 916
Experimental 919
Specimens 919
Test Loading Conditions 919
Creep Testing in Air at 288 °C 920
Creep Testing in DPW at 288 °C 921
Microstructural Characterization 921
Results 922
Creep Testing in Air at 288 °C 922
Creep Testing in DPW at 288 °C 923
Microstructural Characterization of Creep Specimens 925
Discussion 927
Conclusions 930
References 931
60 Corrosion Fatigue Behavior of Austenitic Stainless Steel in a Pure D2O Environment 932
Abstract 932
Introduction 932
Experimental 934
Autoclave CF Testing 934
ToF-SIMS Analysis 934
Hot Vacuum Extraction Measurements 936
Results: CFCGR and Fractography 936
Results: SIMS Measurements for Deuterium Concentration 939
Results: H/D Concentration Using Hot Vacuum Extraction 940
Discussion 941
Measurement Issues 941
Role of Hydrogen/Deuterium in Crack Growth 943
Conclusion 944
References 944
61 Mechanistic Understanding of Environmentally Assisted Fatigue Crack Growth of Austenitic Stainless Steels in PWR Environments 946
Abstract 946
Introduction 947
Materials 948
Experimental 948
Data Presentation 949
Results 950
Saw-Tooth Loading 950
Trapezoidal Loading 952
Multiple Cycles with Hold Periods 955
Hold at maximum load 955
Hold at mean load 958
Load Ratio Effects 959
Characterisation 963
Fracture Surfaces 963
Saw-tooth loading 963
Trapezoidal loading 964
Multiple cycles with hold periods 965
Crack-Tip Analysis 966
Trapezoidal Loading 967
Multiple cycles with long holds 968
Discussion 969
Crack Growth Rates 969
Characterization 971
Mechanistic Implications 972
Conclusions 973
Crack Growth Trends 973
Fracture Morphology Trends 973
Mechanistic Implications 974
References 974
62 Study on Hold-Time Effects in Environmental Fatigue Lifetime of Low-Alloy Steel and Austenitic Stainless Steel in Air and Under Simulated PWR Primary Water Conditions 976
Abstract 976
Introduction 976
Testing 977
Test Material 977
Tests in Air 978
Tests in High-Temperature Water 978
Test Results 980
Results from Tests in Air 980
Results from Tests in High-Temperature Water 982
Summary and Discussion 990
Acknowledgements 993
References 994
Special Topics I—Materials 996
63 Evaluation of Additively Manufactured Materials for Nuclear Plant Components 997
Abstract 997
Introduction 998
Specimen History, Specimen Design, Facility Design and Overview of Testing Procedures 999
Un-irradiated Results 1001
DMLM Type 316L 1001
DMLM Alloy 718 1001
Planned Irradiated Testing and Characterization 1003
Discussion of the DMLM Type 316L and Alloy 718 Results 1007
Conclusions 1008
Acknowledgements 1008
References 1008
64 Hot Cell Tensile Testing of Neutron Irradiated Additively Manufactured Type 316L Stainless Steel 1009
Abstract 1009
Background 1010
Testing Summary 1011
Miniature Tensile Specimen Geometry and Fabrication 1014
Irradiated Material Description 1015
Radiation Measurements of Irradiated Quads 1016
Tensile Testing Approach 1016
Tensile Test Results 1020
Discussion 1021
Conclusions 1025
Acknowledgements 1026
References 1026
65 Computational and Experimental Studies on Novel Materials for Fission Gas Capture 1027
Abstract 1027
Introduction 1028
Nitrogen Adsorption on Single Wall Carbon Nanotubes at Various Conditions 1029
Computational Nanotube Model 1030
Mesoporous Silica 1032
Molecular Dynamics Simulation Methodology 1033
Monte Carlo Simulation 1034
ALD Nickel Experiments 1035
Conclusions 1037
Acknowledgements 1037
References 1037
66 Hydrogen Assisted Cracking Studies of a 12% Chromium Martensitic Stainless Steel—Influence of Hardness, Stress and Environment 1039
Abstract 1039
Introduction 1040
Experimental Method 1041
Materials 1041
Experimental Conditions and Procedures 1042
Atmospheric Four-Point Bend Testing 1042
Fully-Immersed Four-Point Bend Testing 1042
Incremental Step Load Testing 1043
Results 1045
Constant Displacement Testing 1045
Atmospheric Corrosion Testing 1045
Immersion Tests 1047
Incremental Step Loading (ISL) Tests 1049
Discussion 1050
Conclusions 1052
References 1053
67 Investigation of Flow Accelerated Corrosion Models to Predict the Corrosion Behavior of Coated Carbon Steels in Secondary Piping Systems 1054
Abstract 1054
Introduction 1054
Materials and Methods 1055
Preparation of the Coatings 1055
Corrosion Experiments 1056
Mechanistic Models 1056
Results and Discussion 1057
Microstructure Analysis 1057
Corrosion Experiments 1058
Fac Simulation Experiments 1060
Mechanistic Models 1061
Conclusion 1061
Acknowledgements 1062
References 1062
68 Effect of High-Temperature Water Environment on the Fracture Behaviour of Low-Alloy RPV Steels 1064
Abstract 1064
Introduction 1064
Materials and Experiments Procedures 1066
Materials and Specimens 1066
Elastic Plastic Fracture Mechanics 1069
High Temperature Water Environments 1069
Results and Discussion 1071
Biblis C Base Metal Material (Reference Material and Behaviour) 1071
Simulated Coarse Grain Heat Affected Zone Material HT1 with High Yield Stress 1072
Base Metal Material with High DSA Susceptibility 1075
Summary, Conclusions and Outlook 1085
Acknowledgements 1085
References 1086
69 Corrosion Fatigue Testing of Low Alloy Steel in Water Environment with Low Levels of Oxygen and Varied Load Dwell Times 1087
Abstract 1087
Introduction 1087
Experimental 1088
Material and Specimen Information 1088
Test Procedure 1089
Results and Discussion 1090
Specimen Characterization 1090
Fatigue Crack Length Measurement 1090
Effect of Oxygen and Dwell Time on Crack Growth Rate 1091
Conclusions 1093
References 1093
70 Feasibility Study of the Internal Zr/ZrO2 Reference Electrodes in Supercritical Water Environments 1095
Abstract 1095
Introduction 1096
Experimental 1097
Sample Preparation 1097
Test Facility 1097
Mass Change and Surface Analyses of Zr Reference Electrode 1098
Results and Discussion 1099
Zr Mass Change Test Under SCW Environment 1099
Duration Test for Zr 1103
SEM Images Analysis 1106
Conclusions 1107
References 1108
Special Topics II—Processes 1109
71 Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation 1110
Abstract 1110
Introduction 1111
Materials and Methods of Investigation 1112
Alloying 1112
Fabrication 1113
Gravimetric Tests 1115
Experimental Results and Discussion 1115
Microstructural Analysis 1115
Mechanical Properties 1116
Effects of Alloying and Neutron Irradiation on Pitting Corrosion Resistance of 316 LN Steel 1117
Effect of Sensitization and Neutron Irradiation on Pitting Corrosion Resistance of 316 LN Steel Alloyed by Nitrogen, Manganese, Copper and Tungsten 1118
Pitting and Corrosion Resistance of the Steels After GBE 1122
Conclusions 1123
Acknowledgements 1123
References 1124
72 Quantifying Erosion-Corrosion Impacts on Light Water Reactor Piping 1126
Abstract 1126
Introduction 1126
Modeling 1127
Erosion-Corrosion 1127
Erosion Only 1128
Hardness Factor (Fhard) 1129
Temperature Factor (Ftemp) 1130
Particle Shape Factor (Fshape) 1130
Corrosion Only 1132
General Corrosion Rate (Uref) 1132
pH Factor (H) 1132
Velocity Factor (Fvel) 1133
Temperature Factor (R) 1133
Synergy 1134
Probabilistic Versus Deterministic 1135
Sensitivity Analyses 1136
Results 1137
Conclusions 1139
References 1140
73 Effect of Molybdate Anion Addition on Repassivation of Corroding Crevice in Austenitic Stainless Steel 1142
Abstract 1142
Introduction 1142
Experiments 1143
Specimen and Experimental Equipment 1143
Measurement of Initiation Potentials for Crevice Corrosion in Chloride-Contaminated Water with Added Molybdate Anion 1144
Measurement of Repassivation Potentials for Crevice Corrosion in Chloride-Contaminated Water with Added Molybdate Anion 1145
Results and Discussion 1145
Initiation Potential for Crevice Corrosion in Chloride-Contaminated Water with Added Molybdate Anion 1145
Repassivation Potential for Crevice Corrosion in Chloride-Contaminated Water with Added Molybdate Anion 1147
Comparison of Critical Conditions for Repassivation in Initiation/Repassivation Tests 1149
The Suppression Mechanism of Molybdate Anion on Crevice Corrosion 1151
Conclusions 1152
Acknowledgements 1152
References 1153
74 Effect of pH on Hydrogen Pick-Up and Corrosion in Zircaloy-4 1154
Abstract 1154
Introduction 1154
Experimental 1155
Oxidation Versus pH 1157
Hydrogen Pick-Up Versus pH 1159
Conclusions 1163
References 1164
75 Oxidation Kinetics of Austenitic Stainless Steels as SCWR Fuel Cladding Candidate Materials in Supercritical Water 1166
Abstract 1166
Introduction 1167
Experimental Details 1168
Materials and Specimens 1168
Oxidation Experiments in Supercritical Water Environment 1169
Results and Discussion 1170
Oxidation Kinetics of the Austenitic SSs in Supercritical Water 1170
Relationship Between Decrease in Oxidation Kinetics and Cr Enrichment in Oxide Layer 1171
Degradation of Protective Cr2O3 Layer and Nodular Oxidation in the Outmost Surface of the Tube-Shaped 15Cr–20Ni SS 1172
Conclusion 1178
Acknowledgements 1179
References 1179
76 A Recent Look at CANDU Feeder Cracking: High Resolution Transmission Electron Microscopy and Electron Energy Loss Near Edge Structure (ELNES) 1180
Abstract 1180
Introduction 1181
Experimental 1182
Results 1184
Intrados Feeder Crack Tip Characterization 1184
Extrados Feeder Crack-Tip Characterization 1188
Potential Breakdown of Sulfides 1192
Cementite-to-Amorphous Carbon Breakdown 1194
Discussion 1196
Conclusion 1198
Acknowledgements 1199
References 1199
Cables and Concrete Aging and Degradation–Cables 1201
77 Simultaneous Thermal and Gamma Radiation Aging of Electrical Cable Polymers 1202
Abstract 1202
Introduction 1202
XLPE Cable Insulation Material Studied 1203
Differential Scanning Calorimetry 1204
Thermal and Gamma Radiation Aging 1205
Oxidation Induction Time 1205
Gel Fraction and Uptake Factor 1206
Scanning Electron Microscopy 1207
Conclusion 1208
Acknowledgements 1208
References 1209
78 Principal Component Analysis (PCA) as a Statistical Tool for Identifying Key Indicators of Nuclear Power Plant Cable Insulation Degradation 1210
Abstract 1210
Introduction 1210
Sample Preparation 1211
Statistical Analysis Method 1213
Characterization Methods 1214
Mass Loss 1215
Elongation-at-Break 1215
Indenter Modulus 1215
Density 1215
Oxidation Induction Time (OIT) 1216
Results and Discussion 1217
Data 1217
Effect of Total Dose on Irradiated Samples 1217
Conclusions 1221
Acknowledgements 1221
References 1222
79 How Can Material Characterization Support Cable Aging Management? 1223
Abstract 1223
Introduction 1223
Electrical Cable Materials 1225
Test Methods 1225
Near Infrared Spectroscopy 1226
Mid Infrared Spectroscopy 1226
Indenter Modulus 1226
Elongation at Break 1227
Oxidation Induction Time 1227
Results and Discussion 1227
Conclusions 1236
References 1237
80 Aqueous Degradation in Harvested Medium Voltage Cables in Nuclear Power Plants 1239
Abstract 1239
Introduction 1239
Basic and Applied MV Power Cable Research—An Academic and Utility Perspective 1241
Applied MV Power Cable Research—A Nuclear Industry Perspective 1242
ORNL—UMD MV Power Cable Accelerated Aging Technical Approach 1243
Conclusions 1245
Acknowledgements 1246
References 1246
81 Frequency Domain Reflectometry Modeling and Measurement for Nondestructive Evaluation of Nuclear Power Plant Cables 1248
Abstract 1248
Introduction and Background 1248
FDR Theory 1249
Cable and FDR Modeling Prior Work 1252
FDR Simulation Methodology 1253
Validation of Simulation Results 1254
Cable FDR Simulation Study 1256
Insulation Dielectric Constant 1256
Defect Length 1257
Defect Distribution 1258
Conclusions 1259
Future Work 1260
References 1260
82 Aging Mechanisms and Nondestructive Aging Indicator of Filled Cross-Linked Polyethylene (XLPE) Exposed to Simultaneous Thermal and Gamma Radiation 1262
Abstract 1262
Introduction 1263
Sample Preparation 1263
Materials Characterization 1263
Scanning Electron Microscopy (SEM) 1264
Pyrolysis Gas Chromatography—Mass Spectrometry (Pyrolysis GCMS) 1264
Oxidation Induction Time (OIT) 1264
Differential Scanning Calorimetry (DSC) 1264
Dielectric Loss Tangent 1265
Results 1265
Composition Analysis 1265
Characterization Results 1266
Interpretation 1269
Conclusions 1271
Acknowledgements 1272
References 1272
83 Successful Detection of Insulation Degradation in Cables by Frequency Domain Reflectometry 1273
Abstract 1273
Introduction 1273
Principle of the Method 1274
Background and History of Development 1275
Several Examples of Results Obtained in Recent Study 1277
References 1280
84 Capacitive Nondestructive Evaluation of Aged Cross-Linked Polyethylene (XLPE) Cable Insulation Material 1282
Abstract 1282
Introduction 1282
Modeling 1284
Sensor Configuration 1284
Capacitance and Sensitivity 1284
Simulation Setting and Sensitivity Calculation 1285
Results 1287
Univariate Effects 1287
Digit Width (W) 1287
Digit Separation (G) 1287
Digit Number (N) 1288
Combined Effect 1290
Conclusions 1292
Acknowledgements 1292
References 1292
85 Tracking of Nuclear Cable Insulation Polymer Structural Changes Using the Gel Fraction and Uptake Factor Method 1293
Abstract 1293
Introduction 1293
Experimental 1294
Material 1294
Sample Aging and Preparation 1295
Swollen Sample Measurement 1295
Dried Sample Measurement 1296
Results 1296
Gel Fraction 1296
Uptake Factor 1297
Conclusion 1299
References 1299
86 Degradation of Silicone Rubber Analyzed by Instrumental Analyses and Dielectric Spectroscopy 1300
Abstract 1300
Introduction 1300
Experiments 1301
Several Important Experimental Results 1301
Dielectric Spectroscopic Analysis of Degradation 1306
Conclusion 1308
References 1308
Cables and Concrete Aging and Degradation–Concrete 1310
87 Automated Detection of Alkali-Silica Reaction in Concrete Using Linear Array Ultrasound Data 1311
Abstract 1311
Automated Data Analysis of Cracking Due to Alkali-Silica Reaction in Concrete 1312
Frequency Domain Methods and Classification Features 1312
Detection with the Hilbert Transform Indicator 1314
Machine Learning–Based Classification Features/Methods 1315
Artificial Neural Network Background 1315
Development of an Artificial Neural Network Algorithm/Method for Detection of Cracking Due to Alkali-Silica Reaction 1316
Extracting Meaningful Insights from the Artificial Neural Network Algorithm/Method for Detection of Cracking Due to for Alkali-Silica Reaction 1318
Conclusions 1320
Acknowledgements 1321
References 1321
88 Coupled Physics Simulation of Expansive Reactions in Concrete with the Grizzly Code 1322
Abstract 1322
Introduction 1322
Governing Equations 1324
Heat Transfer 1324
Moisture Transfer 1324
Mechanical Deformation 1325
Alkali-Silica Reaction Models 1325
Alkali-Silica Reaction Kinetics 1325
Alkali-Silica Reaction Induced Strains 1326
Anisotropic ASR Strains and Weights in Principal Directions 1328
Multiphysics Solution Environment 1328
Validation 1329
Example Application 1329
Summary 1331
References 1332
89 Overview of EPRI Long Term Operations Work on Nuclear Power Plant Concrete Structures 1333
Abstract 1333
Introduction 1333
Epri Research 1334
Irradiation Damage in Concrete Biological Shielding 1334
Spent Fuel Pool Concrete Degradation 1337
Alkali-Silica Reaction 1338
Conclusion 1339
References 1339
90 The Effects of Neutron Irradiation on the Mechanical Properties of Mineral Analogues of Concrete Aggregates 1340
Abstract 1340
Introduction 1341
Investigated Materials and Experimental Methods 1342
Experimental Results and Discussion 1344
Conclusions 1346
Acknowledgements 1349
References 1349
Accident Tolerant Fuel Cladding 1351
91 Accident Tolerant FeCrAl Fuel Cladding: Current Status Towards Commercialization 1352
Abstract 1352
Introduction 1352
Overview of Materials Database 1355
Summary 1358
Acknowledgements 1358
References 1358
92 Interdiffusion Behavior of FeCrAl with U3Si2 1361
Abstract 1361
Introduction 1361
Experimental 1363
Results and Discussion 1366
Conclusion 1369
Acknowledgements 1370
References 1370
93 Mechanical Behavior of FeCrAl and Other Alloys Following Exposure to LOCA Conditions Plus Quenching 1371
Abstract 1371
Introduction 1371
Experimental Setup and Procedures 1373
Mechanical Behavior 1376
Characterization of Surface Oxides 1380
Summary and Conclusions 1385
Acknowledgements 1385
References 1385
94 Mechanical Behavior and Structure of Advanced Fe-Cr-Al Alloy Weldments 1387
Abstract 1387
Introduction 1387
Investigated Materials and Experimental Methods 1389
Experimental Results 1391
Discussion of Alloying and Weldment Performance 1397
Conclusion 1398
Acknowledgements 1399
References 1399
95 Investigating Potential Accident Tolerant Fuel Cladding Materials and Coatings 1401
Abstract 1401
Introduction 1401
Experimental 1403
Material Preparation 1403
300 °C Water Corrosion Tests 1404
Steam Corrosion Tests 1404
Surface Characterization 1405
Results and Discussion 1406
As-Prepared Samples 1406
Aqueous Corrosion Results 1408
Steam Corrosion Results 1414
Conclusions 1418
References 1419
96 Steam Oxidation Behavior of FeCrAl Cladding 1421
Abstract 1421
Introduction 1422
Experimental Procedure 1422
Results and Discussion 1424
Effect of Alloy Composition on the Steam Oxidation Behavior of FeCrAl Alloys 1424
Steam Oxidation Testing of Model FeCrAl Alloys After Exposure to Hydrothermal Corrosion 1426
Summary 1428
Acknowledgements 1429
References 1429
97 In-Situ Proton Irradiation-Corrosion Study of ATF Candidate Alloys in Simulated PWR Primary Water 1431
Abstract 1431
Introduction 1432
Experiments 1433
Materials 1433
Irradiation 1434
Post Irradiation Characterization 1435
Results 1435
Oxide Morphology 1435
Oxide Species Found in IR/UR Regions 1437
Microstructure Observations 1438
Oxide Composition Analysis 1439
Discussion 1441
Corrosion Mechanism 1441
Oxide Dissolution 1442
Conclusion 1443
Acknowledgements 1443
References 1443
98 Hydrothermal Corrosion of SiC Materials for Accident Tolerant Fuel Cladding with and Without Mitigation Coatings 1445
Abstract 1445
Introduction 1446
Experiment 1446
Samples Prepared 1446
Experimental Procedure 1447
Results 1448
Conclusions 1452
Acknowledgements 1452
References 1453
99 Characterization of the Hydrothermal Corrosion Behavior of Ceramics for Accident Tolerant Fuel Cladding 1454
Abstract 1454
Background 1455
Experimental 1455
Results and Discussion 1456
Alumina Corrosion Characteristics 1456
SiC Corrosion Characteristics 1459
Conclusions 1464
Acknowledgements 1465
References 1465
100 Corrosion of Multilayer Ceramic-Coated ZIRLO Exposed to High Temperature Water 1466
Abstract 1466
Introduction 1466
Experiment 1468
Materials 1468
Corrosion Experiment 1468
Characterization 1468
Results and Discussion 1469
Weight Gain Post SCW Exposure 1469
Characterization of Coating Architecture 1470
Coating Morphology Post Oxidation 1471
Oxidation of Tube OD Beneath the Coating 1473
Conclusions 1476
Acknowledgements 1476
References 1476
General SCC and SCC Modeling 1478
101 Calibration of the Local IGSCC Engineering Model for Alloy 600 1479
Abstract 1479
Background 1479
The ‘Local Model’ 1481
Assumptions 1481
Intergranular Oxidation Rate 1481
Stress Concentration at Grain Boundaries 1483
Initiation 1484
Crack Growth 1484
SCC Computation 1485
Calibration of the Model Parameters 1485
Materials 1485
Intergranular Oxidation Kinetics 1487
Stress Concentration at Grain Boundaries 1490
Initiation Criterion 1492
Crack Growth 1496
Results 1496
Discussion 1499
Conclusions 1500
References 1500
102 Prediction of IGSCC as a Finite Element Modeling Post-analysis 1502
Abstract 1502
Background 1502
New IGSCC Models 1503
Methodology to Predict SCC 1505
Simulating SCC Laboratory Tests 1507
Simulating SCC of Components 1512
Discussion 1514
Conclusions 1516
References 1516
103 Monte Carlo Simulation Based on SCC Test Results in Hydrogenated Steam Environment for Alloy 600 1518
Abstract 1518
Introduction 1519
Stastical Interperetation of PWSCC Data 1520
Reproduction of the Behavior of SCC Occurrence in Hydrogenated Steam by SCC Simulation 1524
Conclusions 1527
References 1527
104 Protection of the Steel Used for Dry Cask Storage System from Atmospheric Corrosion by Tio2 Coating 1529
Abstract 1529
Introduction 1530
Experimental 1530
Preparation of Substrate 1530
Preparation of TiO2 Coating 1531
Characterization 1531
Photoelectrochemical Measurements 1531
Results and Discussion 1531
Effect of Heat Treatment Temperature on the Photovoltage of TiO2 Coated on ITO 1531
Behaviour of Oxide Layer on Carbon Steels Under Different Heat Treatment Condition 1532
Effect of Heat Treatment Temperature on the Photovoltage of TiO2 Coated on Carbon Steel for Different Oxidation Condition 1533
Conclusions 1536
References 1537
105 Predictive Modeling of Baffle-Former Bolt Failures in Pressurized Water Reactors 1538
Abstract 1538
Introduction 1539
Predictive Methodology Development 1541
Weibull Reliability Model 1543
Bolt Stress Model 1546
Cumulative Exposure Model 1547
Bolt Failure Probability Model 1548
Bolt Failure Map 1549
Inspection Restart Model 1549
Predictive Evaluation Results and Discussion 1550
Benchmarking Through Finite Element Modeling 1551
Conclusions 1552
References 1552
106 Technical Basis and SCC Growth Rate Data to Develop an SCC Disposition Curve for Alloy 82 in BWR Environments 1554
Abstract 1554
Introduction 1554
Test Materials 1555
Experimental Procedures 1558
Results and Discussion 1558
Effect of Weld Type 1560
Sample Size Effect 1561
Effect of PWHT 1564
Effect of Sulfate Injection 1565
Remaining Tasks in Alloy 82 Disposition Curve Development 1566
Conclusions 1567
Acknowledgements 1567
References 1567
BWR SCC and Water Chemistry 1569
107 SCC and Fracture Toughness of XM-19 1570
Abstract 1570
Introduction 1571
Experimental Procedures 1572
Results and Discussion—SCC Growth Rate 1574
Results and Discussion—Fracture Toughness 1580
Conclusions 1583
References 1584
108 On the Effect of Preoxidation of Nickel Alloy X-750 1586
Abstract 1586
Introduction 1587
Experimental 1587
Results 1588
Discussion 1592
Conclusion 1595
References 1595
109 Microstructures of Oxide Films Formed in Alloy 182 BWR Core Shroud Support Leg Cracks 1596
Abstract 1596
Introduction 1597
Experimental 1597
Material and Examined Locations 1597
TEM Lamella Liftout with FIB/SEM 1598
TEM Instrumentation 1599
Results 1599
Microstructures of Oxide Films in the Crack Mouth 1599
Microstructures of Oxide Films in the Midway Between the Crack Mouth and Tip 1600
Microstructures of Active Crack Tips 1601
Discussion 1608
Conclusions 1610
Acknowledgements 1610
References 1610
110 Effect of Chloride Transients on Crack Growth Rates in Low Alloy Steels in BWR Environments 1611
Abstract 1611
Introduction 1611
Experimental Procedures 1613
Results 1615
Crack Growth Rate Under Constant Load in Normal Water Chemistry 1615
Crack Growth Rate Under Constant Load in Hydrogen Water Chemistry 1616
Heat-to-Heat Comparison 1616
Chloride Memory Effect on Stress Corrosion Crack of Low Alloy Steel 1618
Conclusions 1622
Acknowledgements 1622
References 1622
111 Electrochemical Behavior of Platinum Treated Type 304 Stainless Steels in Simulated BWR Environments Under Startup Conditions 1624
Abstract 1624
Introduction 1624
Experimental 1626
Results and Discussion 1628
Conclusions 1632
References 1632
112 Investigations of the Dual Benefits of Zinc Injection on Cobalt-60 Uptake and Oxide Film Formation Under Boiling Water Reactor Conditions 1634
Abstract 1634
Introduction 1634
Materials and Methods 1636
Sample Preparation and Oxidation 1636
Microstructural Characterisation 1637
Results 1637
Machined Surface (#600 Grit) 1637
OPS-Polished Surface 1638
Discussion 1642
Machined Surface (#600 Grit) 1642
OPS-Polished Surface 1642
Conclusions 1643
References 1643
113 SCC Mitigation in Boiling Water Reactors: Platinum Deposition and Durability on Structural Materials 1645
Abstract 1645
Introduction 1645
Materials and Methods 1646
Materials 1646
Experimental Set-Up and Procedures 1647
Results and Discussion 1649
Effect of Surface Roughness 1649
Effect of Alloy Composition 1650
Post-application Pt Redistribution 1654
Conclusions 1658
Acknowledgements 1658
References 1659
114 Confirmation of On-Line NobleChem™ (OLNC) Mitigation Effectiveness in Operating Boiling Water Reactors (BWRs) 1661
Abstract 1661
Introduction 1661
Experimental Methods and Plant Specimen History 1663
Surface Characterization Results 1663
MMS Coupons 1664
Reactor Internal Component Artifacts 1665
Tie Rod Latch 1665
Jet Pump Auxiliary Wedge 1666
Bottom Head Drain Line ECP Probes 1667
Fuel Channel Fastener 1668
Summary of Results 1669
Conclusions and Future Work 1671
Acknowledgements 1672
Reference 1672
115 Development of the Fundamental Multiphysics Analysis Model for Crevice Corrosion Using a Finite Element Method 1673
Abstract 1673
Introduction 1673
Overview of Simulation 1674
Results and Discussion 1678
Conclusions 1682
References 1682
116 In Situ Electrochemical Study on Crevice Environment of Stainless Steel in High Temperature Water 1684
Abstract 1684
Introduction 1684
Experimental 1685
Preparation of Crevice Specimen with Sensors 1685
Electrochemical Measurement 1687
Exposure Test to High-Temperature Water 1687
Analysis of Surface Oxide 1687
Results and Discussion 1687
Surface and Electrochemical Analysis with DO of 32 Ppm 1687
Influence of DO Transients 1692
Influence of Na2SO4 and DO Transients 1693
Conclusions 1695
Acknowledgements 1695
References 1696
Zirconium and Fuel Cladding 1697
117 Corrosion Fatigue Crack Initiation in Zr-2.5Nb 1698
Abstract 1698
Introduction 1698
Experimental Procedure 1699
Specimens 1699
Fatigue Tests 1700
Characterization 1701
Results and Discussion 1702
Summary 1712
Acknowledgements 1712
References 1712
118 Cluster Dynamics Model for the Hydride Precipitation Kinetics in Zirconium Cladding 1715
Abstract 1715
Introduction 1716
Model Setup 1717
Results and Discussion 1719
Conclusions 1723
Acknowledgements 1723
References 1723
119 Modeling Corrosion Kinetics of Zirconium Alloys in Loss-of-Coolant Accident (LOCA) 1725
Abstract 1725
Introduction 1725
Coupled Current Charge Compensation (C4) model 1727
Assumptions 1727
Moving Boundary Diffusion Model 1728
Results and Discussion 1729
Parameters Used 1729
Low Temperature Oxidation (360 °C) 1731
Oxide and /alpha -Zr Phase Growth Kinetic at High Temperature 1731
Oxygen Concentration Profile at High Temperature 1733
Conclusion 1734
Acknowledgements 1735
References 1735
120 Progressing Zirconium-Alloy Corrosion Models Using Synchrotron XANES 1736
Abstract 1736
Introduction 1736
Experimental Procedures 1738
Results 1740
Discussion 1741
Comparison with C4 Model 1741
Zr-1.0Nb (580 °C) 1743
Metallic Depth Analysis 1745
Conclusion 1746
Acknowledgements 1747
References 1747
121 Advanced Characterization of Hydrides in Zirconium Alloys 1748
Abstract 1748
Introduction 1749
Experimental 1751
Results 1753
FIB 1753
EELS 1753
TEM 1756
Discussion 1763
Conclusions 1765
References 1766
122 Influence of Alloying Elements and Effect of Stress on Anisotropic Hydrogen Diffusion in Zr-Based Alloys Predicted by Accelerated Kinetic Monte Carlo Simulations 1769
Abstract 1769
Introduction 1770
Methods 1771
DFT Calculations 1771
Accelerated Lattice Kinetic Monte Carlo 1772
Results and Discussion 1772
Results from DFT Calculations 1772
Hydrogen Diffusion in Zr Alloys 1774
Stress Effect on Hydrogen Diffusion 1775
Elastic Dipole Tensor 1777
Conclusion 1778
Acknowledgements 1779
References 1779
Stainless Steel Aging and CASS 1781
123 Influence of ?-Ferrite Content on Thermal Aging Induced Mechanical Property Degradation in Cast Stainless Steels 1782
Abstract 1782
Introduction 1782
Experiment and Analysis 1783
Effect of Aging on Strength and Ductility 1786
Effect of Aging on Impact Toughness 1790
Concluding Remarks 1792
Acknowledgements 1792
References 1792
124 Microstructure and Deformation Behavior of Thermally Aged Cast Austenitic Stainless Steels 1794
Abstract 1794
Introduction 1795
Experimental 1796
Material and Specimens 1796
Fracture Toughness J-R Curve Tests 1797
Microstructural Characterization 1798
Wide-Angle X-Ray Scattering (WAXS) with In Situ Tensile 1798
Results and Discussion 1801
J-R Curve Tests 1801
Microstructural Characterization 1802
In Situ Tensile Tests 1805
Conclusions 1809
Acknowledgements 1809
References 1809
125 Microstructural Evolution of Cast Austenitic Stainless Steels Under Accelerated Thermal Aging 1811
Abstract 1811
Introduction 1811
Methods 1812
Materials and Thermal Aging 1812
Microstructural and Elemental Characterization 1814
Results and Discussion 1814
Conclusion 1819
Acknowledgements 1819
References 1820
126 Electrochemical Characteristics of Delta Ferrite in Thermally Aged Austenitic Stainless Steel Weld 1821
Abstract 1821
Introduction 1822
Materials and Experimental 1822
Results and Discussion 1823
Electrochemical Analysis of 316L ASSW 1823
Selective Austenite Etching 1825
Electrochemical Analysis of ?–Ferrite Phase 1825
Summary 1828
Acknowledgements 1828
References 1828
127 Effect of Long-Term Thermal Aging on SCC Initiation Susceptibility in Low Carbon Austenitic Stainless Steels 1830
Abstract 1830
Introduction 1830
Experimental Procedure 1831
Specimens 1831
Creviced Bent Beam (CBB) Test 1832
Hardness Measurement 1832
TEM Observation and EDX Chemical Composition Analysis Around Grain Boundaries 1832
Experimental Results 1833
CBB Test 1833
Hardness Measurement 1833
TEM Observation and EDX Chemical Composition Analysis Around Grain Boundaries 1834
Surface Examination of CBB-Tested Specimens by Means of SEM 1835
Discussion 1836
Conclusions 1838
References 1839
128 Crack Growth Rate and Fracture Toughness of CF3 Cast Stainless Steels at sim3 DPA 1840
Abstract 1840
Introduction 1840
Experimental Details 1842
Materials and Specimens 1842
Irradiation 1843
Crack Growth Rate and J-R Curve Tests 1843
Results 1844
Cyclic and SCC Crack Growth Rates 1844
Fracture Toughness 1846
Irradiated Microstructure 1848
Discussion 1849
Conclusions 1853
Acknowledgements 1853
References 1853
129 Effects of Thermal Aging and Low Dose Neutron Irradiation on the Ferrite Phase in a 308L Weld 1855
Abstract 1855
Introduction 1856
Experimental Details 1857
Materials and Conditions 1857
Transmission Electron Microscopy 1858
Atom Probe Tomography 1858
Results 1858
Spinodal Decomposition 1859
G-Phase Precipitates 1861
Transmission Electron Microscopy 1865
Discussion 1865
Conclusion 1866
Acknowledgements 1867
References 1867
130 Microstructural Evolution of Welded Stainless Steels on Integrated Effect of Thermal Aging and Low Flux Irradiation 1869
Abstract 1869
Introduction 1870
Experimental 1870
Material 1870
Instrumentation 1871
Focused Ion Beam Scanning Electron Microscopy (FIB/SEM) 1871
Atom Probe Tomography 1871
Results and Discussion 1871
G-Phase Formation 1874
Conclusions 1875
Acknowledgements 1876
References 1876
Welds, Weld Metals, and Weld Assessments 1877
131 The Use of Tapered Specimens to Evaluate the SCC Initiation Susceptibility in Alloy 182 in BWR and PWR Environments 1878
Abstract 1878
Introduction 1879
Experimental 1880
Material and Specimen 1880
Environment and Methodology of the SCC Initiation Tests 1880
EngInit Model Description 1883
Results and Discussion 1884
Surface Cracking Morphology and Crack Distribution 1884
Effect of Strain Rate and Surface Finish 1886
EngInit Model 1890
Summary and Conclusions 1893
Acknowledgements 1894
Appendix: Note on the Real and Apparent Stress Threshold 1894
References 1896
132 Effect of Thermal Aging on Fracture Mechanical Properties and Crack Propagation Behavior of Alloy 52 Narrow-Gap Dissimilar Metal Weld 1898
Abstract 1898
Introduction 1899
Experimental Methods 1900
Results 1902
Fracture Mechanical Testing 1902
Fracture Surface and Crack Path Characterization 1904
Discussion 1909
Conclusions 1910
Acknowledgements 1911
References 1911
133 Distribution and Characteristics of Oxide Films Formed on Stainless Steel Cladding on Low Alloy Steel in Simulated PWR Primary Water Environments 1913
Abstract 1913
Introduction 1914
Experimental Procedure 1914
Materials 1914
Immersion Tests in Simulated PWR Primary Water Environments 1916
Results and Discussion 1916
Microstructure Observation 1916
Relationship Between Microstructure and Distribution of Oxide Film 1918
Tests in the Oxygen-Containing PWR Water 1918
Immersion in the Deaerated High Temperature Water at 290 ? for 168 H 1919
The Effect of Oxygen Content on the Oxide Film of Welding 1921
Conclusions 1924
Acknowledgements 1925
References 1925
134 Microstructural Characterization of Alloy 52 Narrow-Gap Dissimilar Metal Weld After Aging 1927
Abstract 1927
Introduction 1927
Experimental Methods 1929
Results 1931
Characterization of the SA 508 HAZ 1931
Characterization of Alloy 52 Weld Metal 1933
Characterization of the Ferritic-Austenitic Interface 1935
Micro- and Nanohardness Profiles 1935
Discussion 1937
Conclusions 1939
Acknowledgements 1940
References 1940
135 A Statistical Analysis on Modeling Uncertainty Through Crack Initiation Tests 1942
Abstract 1942
Introduction 1943
Theoretical Background of the Weibull Distribution 1944
Extremal Types Theorem 1944
Weibull Distribution 1945
Estimation of Weibull Parameters 1947
Monte Carlo Simulation 1948
Experimental Factors 1948
True Weibull Parameters 1948
Number of Specimens 1949
End Cracking Fraction 1949
Length of Censoring Interval 1949
Simulation Procedure 1950
Results and Discussion 1951
Uncertainty of /hat{{/varvec /beta }}_{{{/varvec MLE}}} 1952
Uncertainty of /hat{{/varvec /eta }}_{{{/varvec MLE}}} 1952
Conclusions 1957
Acknowledgements 1957
References 1957
Plant Operating Experience 1959
136 Laboratory Analysis of a Leaking Letdown Cooler from Oconee Unit 3 1960
Abstract 1960
Introduction 1960
Letdown Cooler Description and Metallurgy 1961
Letdown Cooler Operating Conditions 1962
Results 1962
Receipt, Dewatering, and Pressure Testing 1962
Cooler Disassembly 1963
Visual Examinations on Leaking Tube Section 1965
SEM/EDS Examinations 1966
Opened Through-Wall Crack 1968
OD Deposits 1970
Secondary Crack Cross Section 1970
Metallographic Examinations 1971
Through-Wall Crack Tip 1972
Secondary Crack 1973
Vickers Microhardness 1973
Optical Emission Spectroscopy (OES) 1974
Analysis of OD Deposits 1974
Discussion 1974
Material 1975
Tensile Stress 1976
Environment 1976
Conclusions 1978
References 1978
137 Root Cause Analysis of Cracking in Alloy 182 BWR Core Shroud Support Leg Cracks 1980
Abstract 1980
Introduction 1980
Experimental 1981
Material and Examined Locations 1981
Equipment 1982
Results 1982
Crack Path and Microstructure 1982
SEM-EDS/EBSD 1984
Mechanical Properties 1987
Conclusions 1990
Acknowledgements 1990
References 1990
138 Microbially Induced Corrosion in Firefighting Systems—Experience and Remedies 1991
Abstract 1991
Introduction 1991
Background on the Leak in a NPP Firefighting Water System 1994
Failure Analyses of the Firefighting System Leak 1994
Results from the Failure Analysis 1995
Discussion 1998
Remedies and Implications 1999
Acknowledgements 2000
References 2000
139 Managing the Ageing Degradation of Concealed Safety Relevant Cooling Water Piping in European S/KWU LWRs 2001
Abstract 2001
Background: The EU Topical Peer Review 2017—Ageing Management (AM) 2002
AM in German NPPs 2002
Scope of Ageing Management for Concealed Pipework 2003
AM Approach for Safety Relevant Cooling Water Lines 2004
Requirements and Specifications of Safety Relevant Cooling Water Lines 2005
Safety Relevant Cooling Water Lines: Damage Mechanisms 2006
Operational Experience 2007
Monitoring and NDT 2009
Discussion and Summary 2011
Acknowledgements 2011
References 2011
140 Identification of PWR Stainless Steel Piping Safety Significant Locations Susceptible to Stress Corrosion Cracking 2013
Abstract 2013
Purpose 2013
Background 2014
Methodology 2015
Justified Assumptions 2016
Results 2018
Plant A (B& W Unit) Results
Plant B (Westinghouse Unit) Results 2024
Plant C (CE Unit) Results 2028
Discussion & Conclusions
References 2038
IASCC Testing—Characterization 2039
141 On the Use of Density-Based Algorithms for the Analysis of Solute Clustering in Atom Probe Tomography Data 2040
Abstract 2040
Introduction 2041
Experimental 2044
Results 2045
Cluster Identification 2045
Cluster Composition 2048
Discussion and Recommendations 2050
Cluster Detection and Counting 2051
Cluster Composition 2052
Conclusions 2054
Acknowledgements 2055
References 2055
142 Comparative Study on Short Time Oxidation of Un-Irradiated and Protons Pre-Irradiated 316L Stainless Steel in Simulated PWR Water 2057
Abstract 2057
Introduction 2057
Experimental Methods 2059
Materials 2059
Experimental Protocols 2059
Sample Preparation 2059
Proton Irradiation 2060
EBSD Mapping 2061
Oxidation Procedure 2061
Experimental Techniques 2062
Macroscopic Studies 2062
Microscopic Studies 2062
Results 2062
Surface Observations Using Optical Microscopy 2062
Metallographic Observations 2062
Observations Using the Crystallographic Orientation of the Underlying Metal 2062
Surface Observations Using SEM 2064
Un-Irradiated Area Without Cold-Working 2064
Un-Irradiated Area with Cold-Working 2066
Irradiated Area Without Cold-Working 2069
Discussion 2071
Effect of Oxidation Time 2071
Crystallographic Orientation Effect 2072
Inclusions Effect 2072
Cold-Work Effect 2073
Irradiation Effect 2073
Conclusion 2074
Acknowledgements 2075
References 2075
143 Hydrogen Trapping by Irradiation-Induced Defects in 316L Stainless Steel 2077
Abstract 2077
Introduction 2078
Materials and Methods 2079
Materials 2079
Reference Material 2079
Implanted Material 2080
TEM Observations 2080
Cathodic Charging at 25 ? and Aging 2082
TDS 2083
SIMS 2083
Results and Discussion 2083
Microstructural Characterization 2083
Reference Samples 2083
Fe3+ Implanted Samples 2084
Hydrogen Trapping by Irradiation-Induced Defects 2085
Simulation of Diffusion and Trapping 2087
Determination of the Diffusion Constants 2087
Diffusion and Trapping of Deuterium in the Implanted Material 2089
Conclusion 2091
Acknowledgements 2092
References 2092
144 Grain Boundary Oxidation of Neutron Irradiated Stainless Steels in Simulated PWR Water 2094
Abstract 2094
Introduction 2094
Experimental Procedure 2095
Test Materials 2095
Analysis 2096
Experimental Results 2097
Surface Oxidation 2097
Inner Layer Thickness 2097
Cross-Sectional Observation of Gb Oxidation 2098
Gb Oxide Structure and Chemical Composition 2099
Discussion 2101
Conclusions 2103
References 2103
145 Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments—Part I: Microstructure Characterization 2105
Abstract 2105
Introduction 2105
Experimental 2106
Results 2108
As-Received Microstructure 2108
Grain Structure 2108
Second Phases 2109
Radiation-Induced Microstructure 2111
Dislocation Loops 2111
Precipitates 2112
Radiation-Induced Segregation 2112
Discussion 2114
Conclusions 2115
Acknowledgements 2115
References 2115
146 Irradiation Assisted Stress Corrosion Cracking (IASCC) of Nickel-Base Alloys in Light Water Reactors Environments Part II: Stress Corrosion Cracking 2117
Abstract 2117
Introduction 2117
Experimental 2118
Materials and Samples Design 2118
Proton Irradiation Experiment 2118
Hardness Measurement 2120
CERT Test and Crack Characterization 2120
Results 2121
Irradiation Hardening 2121
CERT Test Results 2121
Cracking Behavior 2122
IASCC Susceptibility 2124
Discussion 2125
Conclusion 2127
Acknowledgements 2127
Reference 2127
147 Solute Clustering in As-irradiated and Post-irradiation-Annealed 304 Stainless Steel 2129
Abstract 2129
Introduction 2130
Experimental Method 2130
Results and Discussion 2132
Dislocation Loops by TEM 2132
Solute Distributions by APT 2132
Cu-Rich Clusters 2135
Ni/Si-Rich Clusters 2136
PIA Effect on Irradiation Hardening 2141
The Dispersed Barrier Model 2144
Conclusions 2145
Acknowledgements 2146
References 2146
IASCC Testing—Initiation and Growth 2148
148 Irradiation-Assisted Stress Corrosion Cracking Initiation Screening Criteria for Stainless Steels in PWR Systems 2149
Abstract 2149
Introduction 2149
IASCC Initiation Data Sources 2151
Analysis of PWR IASCC Initiation Data Trends 2152
Summary 2155
Acknowledgements 2155
References 2156
149 Novel Technique for Quantitative Measurement of Localized Stresses Near Dislocation Channel—Grain Boundary Interaction Sites in Irradiated Stainless Steel 2159
Abstract 2159
Introduction 2159
Experimental Procedures 2162
Results and Discussion 2164
Conclusions 2166
Acknowledgements 2167
References 2167
150 IASCC Susceptibility of 304L Stainless Steel Irradiated in a BWR and Subjected to Post Irradiation Annealing 2168
Abstract 2168
Introduction 2168
Experiment 2169
Results and Discussion 2171
Irradiation Hardening 2171
Tensile Straining 2172
Localized Deformation 2173
IASCC Susceptibility 2175
Conclusions 2177
Acknowledgements 2178
References 2178
151 Irradiation Assisted Stress Corrosion Cracking Susceptibility of Alloy X-750 Exposed to BWR Environments 2180
Abstract 2180
Introduction 2180
Experimental Procedures 2181
Material and Irradiation Conditions 2181
Fracture Toughness and IASCC Testing 2181
Tensile Testing 2183
Results and Discussion 2184
Tensile Tests 2184
Fracture Toughness 2185
SCC and IASCC Testing 2186
Conclusions 2190
Acknowledgements 2190
References 2190
152 Evaluation of Crack Growth Rates and Microstructures Near the Crack Tip of Neutron-Irradiated Austenitic Stainless Steels in Simulated BWR Environment 2191
Abstract 2191
Introduction 2191
Experimental Procedure 2192
Specimens 2192
Crack Growth Rate Tests 2192
Microstructural Observations 2194
Results and Discussion 2195
Crack Growth Rates 2195
Microstructures 2199
Summary 2205
Acknowledgements 2205
References 2206
153 Effect of Specimen Size on the Crack Growth Rate Behavior of Irradiated Type 304 Stainless Steel 2207
Abstract 2207
Introduction 2207
Material and Specimens 2209
Test Systems 2211
Test Procedures 2211
Crack Growth Rate Results 2212
Small Specimen S4A 2212
Small Specimen S4B 2214
Large Specimen L1 2215
Discussion 2218
Conclusions 2222
Acknowledgements 2223
References 2223
154 Plastic Deformation Processes Accompanying Stress Corrosion Crack Propagation in Irradiated Austenitic Steels 2225
Abstract 2225
Introduction 2226
Experimental Procedure 2226
Experimental Results and Discussion 2228
Conclusions 2235
References 2235
PWR Oxides and Deposits 2237
155 Effect of Grain Orientation on Irradiation Assisted Corrosion of 316L Stainless Steel in Simulated PWR Primary Water 2238
Abstract 2238
Introduction 2238
Experiment 2239
Sample Design 2240
Corrosion Cell 2241
Characterization 2241
Results and Discussion 2242
Conclusions 2246
Acknowledgements 2247
References 2247
156 Finite Element Modelling to Investigate the Mechanisms of CRUD Deposition in PWR 2248
Abstract 2248
Introduction 2248
Electrokinetic Mechanism 2249
Model Set-up 2251
Results and Discussion 2253
Deposition Initiation—Stage 1 2253
Current Path 2253
Overpotential and Normal Current Density 2254
Deposition Propagation—Stage 2 2255
Deposition Propagation—Stage 3 2256
Comparison Between Stage 2 and 3 2257
Conclusions 2258
References 2259
157 Properties of Oxide Films on Ni–Cr–xFe Alloys in a Simulated PWR Water Environment 2261
Abstract 2261
Introduction 2261
Experimental 2263
Materials 2263
Immersion Tests 2263
Characterization of the Oxide Films 2264
Results 2264
Surface Morphologies and Compositions 2264
Cross-Sectional Morphologies and Compositions 2264
Discussion 2268
Effects of the Iron Content in the Alloys on the Outer Oxide Layer 2268
Effects of the Iron Content in the Alloys on the Inner Oxide Layer 2272
Conclusions 2273
Acknowledgements 2273
References 2273
PWR Secondary Side 2277
158 Effect of Applied Potential and Inhibitors on PbSCC of Alloy 690TT 2278
Abstract 2278
Introduction 2279
Experimental Description 2280
Results and Discussion 2283
Effect of Applied ECP—pH330 °C 8.5 2283
Effect of Applied ECP—pH330 °C 9.5 2286
Inhibitor Scoping Testing 2289
Conclusion 2292
References 2292
159 Corrosion of SG Tube Alloys in Typical Secondary Side Local Chemistries Derived from Operating Experience 2294
Abstract 2294
Introduction 2295
Experimental Frame 2296
Preliminary Results 2300
Checking of OLI Computation Relevance 2300
Surface Conditions After Pre-oxidation in Nominal AVT Water 2300
Results at the End of 2016 2300
Microscopy Examinations of Cross-Sections of Specimen Tested at PHT of 4 2304
SEM Scale 2304
TEM Analysis 2306
Discussion 2308
Conclusions 2310
Acknowledgements 2310
References 2311
160 Investigation on the Effect of Lead (Pb) on the Degradation Behavior of Passive Films on Alloy 800 2313
Abstract 2313
Introduction 2313
Experimental Details 2315
Sample Preparation 2315
Pre-Passivation Under All Volatile Treatment Conditions 2315
Preparation of Pb-Free and Pb-Containing Passive Films 2315
Characterization of the Pb-Free and Pb-Containing Passive Films 2316
Results and Discussion 2318
Cyclic Polarization and Potentiostatic Polarization 2318
Mott-Schottky Analysis 2320
Surface Analysis 2322
Conclusions 2325
Acknowledgements 2327
References 2327
161 Influence of Alloying on ?-?? Phase Separation in Duplex Stainless Steels 2330
Abstract 2330
Introduction 2331
Methods 2331
Materials 2331
Atom Probe Tomography 2332
Nanoindention 2332
Results 2333
Cr Distribution 2333
Amplitude 2334
Nanoindentation 2334
Discussion 2335
Conclusions 2338
Acknowledgements 2339
References 2339
162 Stress Corrosion Cracking of Alloy 800 in Secondary Side Crevice Environment 2340
Abstract 2340
Introduction 2340
Test Method 2341
Materials 2341
Environment 2341
Crack Growth Rate Test Method 2342
Results and Discussion 2343
Fracture Surface Characterization 2343
Temperature Dependence of Growth Rate 2345
Conclusions 2348
Acknowledgements 2349
References 2349
163 Using Modern Microscopy to “Fingerprint” Secondary Side SCC in Ni–Fe Alloys 2351
Abstract 2351
Introduction 2352
Development of Methodology 2353
Caustic Cracking 2355
Alloy 800 2356
Alloy 690TT 2358
Lead-Caustic Cracking 2359
Alloy 800 2359
Alloy 690TT 2363
Acidic Cracking with Pb and/or S 2366
Alloy 800 2366
Alloy 690TT 2370
“Fingerprint” Concept and Future Outlook 2372
Summary and Conclusions 2375
Acknowledgements 2377
References 2377
Appendix 18th International Conference on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors: Questions and Answers 2382
Monday, August 14, 2017 2382
Session: Plenary 2382
A Technology Driven Future 2382
Session: Accident Tolerant Fuel Cladding 2383
Accident Tolerant FeCrAl Fuel Cladding: Current Status Towards Commercialization 2383
Mechanical Behavior of FeCrAl and Other Alloys Following Exposure to LOCA Conditions Plus Quenching 2383
Investigating Potential Accident Tolerant Fuel Cladding Materials and Coatings 2384
Steam Oxidation Behavior of FeCrAl Cladding 2384
In Situ Proton Irradiation-Corrosion Study of ATF Candidate Alloys in Simulated PWR Primary Water 2384
Hydrothermal Corrosion of SiC Materials for Accident Tolerant Fuel Cladding with and Without Mitigation Coatings 2384
Characterization of the Hydrothermal Corrosion Behavior of Ceramics for Accident Tolerant Fuel Cladding 2384
Corrosion of Multilayer Ceramic-Coated ZIRLO Exposed to High Temperature Water 2385
Session: General SCC and SCC Modeling—Part 1 2385
Calibration of the Local IGSCC Engineering Model for Alloy 600 2385
Prediction of IGSCC as a Finite Element Modeling Post-analysis 2385
Session: PWR Nickel SCC—SCC 2385
Scoring Process for Evaluating Laboratory PWSCC Crack Growth Rate Data of Thick-Wall Alloy 690 Wrought Material and Alloy 52, 152, and Variant Weld Material 2385
Applicability of Alloy 690/52/152 Crack Growth Testing Conditions to Plant Components 2386
SCC of Alloy 152/52 Welds Defects, Repairs and Dilution Zones in PWR Water 2387
Status of U.S. NRC Research Activities for Alloy 690/52/152 Crack Growth Rate Testing 2388
Stress Corrosion Cracking of 52/152 Weldments Near Dissimilar Metal Weld Interfaces—Possible Paths for Fast IG SCC Propagation 2388
Stress Corrosion Crack Growth Rate: Testing of Composite Material Specimens 2389
Investigation of Hydrogen Behavior in Relation to the PWSCC Mechanism in Alloy TT690 2390
Session: PWR Nickel SCC—Initiation—Part 1 2391
Crack Initiation Data of Alloy 600 in PWR Water 2391
SCC Initiation Behavior of Alloy 182 in PWR Primary Water 2391
In Situ Evaluation of Multiple Stress Corrosion Cracks by X-Ray Computed Micro-Tomography and Digital Image Correlation 2392
SCC Crack Initiation in Nickel Based Alloy Welds in Hydrogenated Steam at 400 °C 2392
Session: Irradiation Damage—Stainless Steel 2393
Effect of Strain Rate and High Temperature Water on Deformation Structure of VVER Neutron Irradiated Core Internals Steel 2393
Radiation-Induced Precipitates in a Self-ion Irradiated Cold-Worked 316SS Used for PWR Baffle-Bolts 2394
In Situ and Ex Situ Observations of the Influence of Twin Boundaries on Heavy Ion Irradiation Damage Effects in 316L Austenitic Stainless Steels 2394
In Situ Microtensile Testing for Ion Beam Irradiated Materials 2395
Development of High Irradiation Resistance and Corrosion Resistance Oxide Dispersion Strengthened Austenitic Stainless Steels 2395
Session: Irradiation Damage—Swelling 2396
Formation of He Bubbles by Repair-Welding in Neutron-Irradiated Stainless Steels Containing Surface Cole-Worked Layer 2396
Emulating Neutron-Induced Void Swelling in Stainless Steels Using Ion Irradiation 2396
Void Swelling Screening Criteria for Stainless Steels in PWR Systems 2396
Theoretical Study of Swelling of Structural Materials in Light Water Reactors at High Fluencies 2397
Tuesday, August 15, 2017 2397
Session: PWR Nickel SCC—Initiation—Part II 2397
The Effect of Surface Condition on Primary Water Stress Corrosion Cracking Initiation of Alloy 600 2397
Microstructural Effects on SCC Initiation in Cold-Worked Alloy 600 in Simulated PWR Primary Water 2397
Session: PWR Nickel SCC—Aging Effects 2398
A Kinetic Study of Order-Disorder Transition in Ni–Cr Based Alloys 2398
The Role of Stoichiometry on Ordering Phase Transformations in Ni–Cr Alloys for Nuclear Applications 2399
The Effect of Hardening via Long Range Order on the SCC and LTCP Susceptibility of a Nickel-30Chromium Binary Alloy 2400
PWSCC Initiation of Alloy 600: Effect of Long-Term Thermal Aging and Triaxial Stress 2401
Stress Corrosion Cracking of Alloy 718 Subjected to Various Thermal Mechanical Treatments in Primary Water 2401
Time to Fracture Studies of Alloy 718 in PWR Chemical Conditions with Neutrons 2401
Development of Short-Range Order and Intergranular Carbide Precipitation in Alloy 690 TT upon Thermal Aging 2402
Session: Irradiation Damage—Nickel Based and Low Alloy 2402
High Resolution Transmission Electron Microscopy of Irradiation Damage in Inconel X-750 2402
In Situ SEM Push-to-Pull Micro-Tensile Testing of Ex-Service Inconel X-750 2403
Microstructural Characterization of Proton-Irradiated 316 Stainless Steels by Transmission Electron Microscopy and Atom Probe Tomography 2404
Session: PWR Oxides and Deposits 2405
Irradiation Accelerated Corrosion of Stainless Steel in Simulated PWR Primary Water 2405
Session: General SCC and SCC Modeling—Part II 2405
Protection of the Steel Used for Dry Cask Storage System from Atmospheric Corrosion by TiO2 Coating 2405
Predictive Modeling of Baffle Former Bolt Failures in Pressurized Water Reactors 2406
Technical Basis and SCC Growth Rate Data to Develop SCC Disposition Curve for Alloy 82 in BWR Environments 2407
Session: Special Topics II—Processes 2407
Investigation of Pitting Corrosion in Sensitized Modified High-Nitrogen 316LN Steel After Neutron Irradiation 2407
Erosion-Corrosion Impacts on Light Water Reactor Piping 2407
Effect of Molybdate Anion Addition on Repassivation of Corroding Crevice in Austenitic Stainless Steel 2408
Wednesday, August 16, 2017 2409
Session: PWR Nickel SCC—Alloy 60 Mechanistic 2409
Diffusion Processes as a Possible Mechanism for Cr Depletion at SCC Crack Tip 2409
Role of Grain Boundary Cr5B3 Precipitates on Intergranular Attack in Alloy 600 2410
Exploring Nanoscale Precursor Reactions in Alloy 600 in H2–H2O Vapor Using In Situ Analytical Transmission Electron Microscopy 2410
Electrochemical and Microstructural Characterization of Alloy 600 in Low Pressure H2-Steam 2410
Effect of Dissolved Hydrogen on the Crack Growth Rate and Oxide Film Formation at the Crack Tip of Alloy 600 Exposed to Simulated PWR Primary Water 2411
A Mechanistic Study of the Effect of Temperature on Crack Propagation in Alloy 600 Under PWR Primary Water Conditions 2411
Session: PWR Nickel SCC—Alloy 690 Mechanistic 2412
Grain Boundary Damage Evolution and SCC Initiation of Cold-Worked Alloy 690 in Simulated PWR Primary Water 2412
PWSCC Susceptibility of Alloy 690, 52 and 152 2413
Relationship Among Dislocation Density, Local Strain Distribution, and PWSCC Susceptibility of Alloy 690 2413
Morphology Evolution of Grain Boundary Carbides Precipitated Near Triple Junctions in Highly Twinned Alloy 690 2413
The Mechanistic Study on the Stress Corrosion Crack Propagation for Heavily Cold Worked TT Alloy 690 2413
Session: PWR Stainless Steel SCC and Fatigue—SCC—Part I 2414
Microstructural Effects on Stress Corrosion Initiation in Austenitic Stainless Steel in PWR Environments 2414
Oxidation and SCC Initiation Studies of Type 304L SS in PWR Primary Water 2415
SCC Initiation in Stainless Steels with Machined Surface in PWR Primary Water 2415
Session: BWR SCC and Water Chemistry 2415
SCC of XM-19 in 288 °C BWR Water and J-R Response in 288 °C Air 2415
On the Effect of Preoxidation of Nickel Alloy X-750 2416
Microstructures of Oxide Films Formed in Alloy 182 BWR Core Shroud Support Leg Cracks 2416
Effect of Chloride Transients on Crack Growth Rates in Low Alloy Steels in BWR Environments 2416
Electrochemical Behavior of Platinum Treated Type 304 Stainless Steels in Simulated BWR Environments Under Startup Conditions 2417
Investigations of the Dual Benefits of Zinc Injection on 60Co Uptake and Oxide Film Formation Under Boiling Water Reactor Conditions 2418
SCC Mitigation in Boiling Water Reactors: Platinum Deposition and Durability on Structural Materials 2418
Session: Stainless Steel Aging and Class 2419
Influence of ?-Ferrite Content on Thermal Aging Induced Mechanical Property Degradation in Cast Stainless Steels 2419
Microstructure and Deformation Behavior of Thermally Aged Cast Austenitic Stainless Steels 2419
Effect of Long-Term Thermal Aging on SCC Initiation Susceptibility in Low Carbon Austenitic Stainless Steels 2419
Effect of Thermal Aging and Low Dose Neutron Irradiation on the Ferrite Phase in 308L Weld 2420
Microstructural Evolution of Welded Stainless Steels on Integrated Effect of Thermal Aging and Low Flux Irradiation 2420
Session: Zirconium and Fuel Cladding 2420
Corrosion Fatigue Crack Initiation in Zr-2.5Nb 2420
Cluster Dynamics Model for the Hydride Precipitation Kinetics in Zirconium Cladding 2421
Modeling Corrosion Kinetics of Zirconium Alloys in Loss-of-Coolant Accident (LOCA) 2421
Progressing Zirconium-Alloy Corrosion Models Using Synchrotron XANES 2421
Advanced Characterization of Hydrides in Zirconium Alloys 2422
Effect of Alloying Elements and Stress on Hydrogen Diffusion in Zr Alloys 2424
Session: Welds, Weld Metals, and Weld Assessments 2424
Effect of Thermal Aging on Fracture Mechanical Properties and Crack Propagation Behavior of Alloy 52 Narrow-Gap Dissimilar Metal Weld 2424
Microstructural Characterization of Alloy 52 Narrow-Gap Dissimilar Metal Weld After Aging 2424
Session: Special Topics I—Materials—Part I 2425
Evaluation of Additively Manufactured Materials for Use as Nuclear Plant Components 2425
Hot Cell Tensile Testing of Neutron Irradiated Additively Manufactured Type 316L Stainless Steel 2426
Thursday, August 17, 2017 2427
Session: PWR Stainless Steel SCC and Fatigue—SCC—Part II 2427
High-Resolution Characterisation of Austenitic Stainless Steel in PWR Environments: Effect of Strain and Surface Finish on Crack Initiations and Propagation 2427
SCC of ASS Under off-Normal Water Chemistry and Surface Conditions—Part I 2427
SCC of Austenitic Stainless Steels Under Off-Normal Water Chemistry and Surface Conditions—Part II 2428
Session: PWR Stainless Steel SCC and Fatigue—Fatigue 2428
The Effect of Load Ratio on the Fatigue Crack Growth Rate of Type 304 Stainless Steels in Air and High Temperature Deaerated Water at 482 °F 2428
Corrosion Fatigue Behavior of Austenitic Stainless Steel in Pure D2O Environment 2429
Session: PWR Secondary Side 2429
Environmentally Assisted Fatigue Crack Growth of Austenitic Stainless Steels in PWR Environments 2429
Study on Hold-Time Effects in EAF 2429
Effect of Applied Potential and Inhibitors on PbSCC of Alloy 690TT 2429
Secondary Side Corrosion of SG Tube Alloys in Typical Secondary Side Chemistries 2430
Session: Plant Operating Experience 2430
Root Cause Analysis of Cracking in Alloy 182 BWR Core Shroud Support Leg Cracks 2430
Microbially Induced Corrosion in Fire Fighting Systems—Experience and Remedies 2431
Managing the Aging Degradation of Concealed Safety Relevant Cooling Water Piping in European S/KWU LWRs 2431
Session: Cables and Concrete Aging and Degradation—Cables 2432
Simultaneous Thermal and Gamma Radiation Aging of Electrical Cable Polymers 2432
Principal Component Analysis (PCA) as a Statistical Tool for Identifying Key Indicators of Nuclear Power Plant Cable Insulation Degradation 2432
How Can Material Characterization Support Cable Aging Management? 2433
Aqueous Degradation in Harvested Medium Voltage Cables in Nuclear Power Plants 2433
Session: Cables and Concrete Aging and Degradation—Concrete 2433
Aging Mechanisms and Nondestructive Aging Indicator of Commercial Filled Cross-Linked Polyethylene Cable Insulation Materials 2435
Successful Detection of Insulation Degradation in Cables by Frequency Domain Reflectometry 2435
Capacitive Nondestructive Evaluation of Aged Cross-Linked Polyethylene (XLPE) Cable Insulation Material 2435
Session: Special Topics I—Materials—Part II 2436
Corrosion Fatigue Testing of Low Alloy Steel in Water Environment with Low Levels of Oxygen and Varied Load Dwell Times 2436
Session: IASCC Testing—Characterization 2436
Hydrogen Trapping by Irradiation-Induced Defects 2436
Grain Boundary Oxidation of Neutron Irradiated Stainless Steels in Simulated PWR Water 2437
Session: IASCC Testing—Initiation and Growth 2437
Irradiation-Assisted Stress Corrosion Cracking (IASCC) of Nickel-Based Alloy in Light Water Reactors Environments Part II: Stress Corrosion Cracking 2437
Irradiation-Assisted Stress Corrosion Cracking Initiation Screening Criteria for Stainless Steel in PWR Systems 2438
Quantitative Measurement of Localized Stresses Near Dislocation Channel—Grain Boundary Interaction Sites in Irradiated Stainless Steel 2439
IASCC Susceptibility of 304L Stainless Steel Irradiated in a BWR and Subjected to Post-irradiation Annealing 2439
Effect of Specimen Size on the Crack Growth Rate Behavior of Irradiated Type 304 Stainless Steel 2440
Author Index 2441
Subject Index 2447