environmentally-assisted cracking corrosion fatigue and ...specific forms of corrosion 1. general or...
TRANSCRIPT
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Environmentally-assisted Cracking
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
Corrosion Fatigue andIntroduction to SCC
Note: While this course does not contain proprietary BWRVIP or MRP information, per se, it does contain open literature information that was used in the creation of BWRVIP or MRP documents or
BWRVIP or MRP information that was subsequently made non-proprietary via publication, etc.
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Corrosion Fatigue and SCCLearning Objectives
• Understand the mechanism of corrosion fatigue vs. mechanical fatigue
♦ BWR feedwater nozzle
♦ BWR steam dryer brackets
♦ PWR steam generator feedwater nozzle cracking
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 2
♦ PWR steam generator feedwater nozzle cracking
• Understand the fundamental SCC mechanism♦ Susceptible material, corrosive environment
and tensile stress
♦ SCC testing
♦ SCC initiation vs. SCC propagation
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Specific Forms of Corrosion
1. General or uniform corrosion
2. Galvanic corrosion
3. De-alloying corrosion
4. Velocity phenomena - erosion corrosion,
cavitation, impingement, fretting and FAC
MacroLocalized Corrosion
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 3
cavitation, impingement, fretting and FAC
5. Crevice corrosion
6. Pitting corrosion
7. Intergranular corrosion
8. Corrosion fatigue
9. Stress corrosion cracking
Micro Localized Corrosion
Microbiological activity can affect all of the above
MechanicalEffects
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Environmentally-assisted Cracking
• EAC♦ Corrosion fatigue♦ Stress corrosion cracking (SCC)
° Intergranular stress corrosion cracking (IGSCC)– BWR IGSCC– Primary water stress corrosion cracking (PWSCC)
Irradiation assisted stress corrosion cracking (IASCC)
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
– Irradiation assisted stress corrosion cracking (IASCC) – Interdendritic stress corrosion cracking (IDSCC)– Low potential stress corrosion cracking (LPSCC)
° Transgranular stress corrosion cracking (TGSCC)• Criterion for EAC propagation:
♦ There is a mechanism to protect the crack sides♦ If this is not met, then the incipient sharp crack will
devolve into a blunt notch and will arrest♦ Criterion is readily met in passive alloys
PRS-11-037 F BMG/ 4
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Fatigue
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
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Mechanical Fatigueand Corrosion Fatigue
• Fatigue #1 cause of metallic failures
• Fatigue is the tendency of a metal to fracture under repeated cyclic loading♦ SCC is due to static loading
Corrosion fatigue is mechanical fatigue
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 6
• Corrosion fatigue is mechanical fatigue aggravated by corrosion reactions
• All environments will reduce the fatigue life of a component and can eliminate any fatigue/endurance limit
• CF is a non-environment specific cracking phenomenon (unlike SCC!)
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Example of Mechanical Fatigue
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 7
Open University
Where better to show fatigue due to cyclic stresses than a bicycle!
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Mechanical Fatigueand Corrosion Fatigue
• Cracks formed by CF are usually wider and less uniform in appearance than mechanical fatigue because of the metal removed by corrosion
• Initiation may occur at multiple sites
• Microscopically, the cracks are typically transgranular following the load usually oxide filled
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 8
transgranular following the load, usually oxide-filled and blunt-tipped, with irregular crack profiles and signs of discontinuous propagation
• Similar to purely fatigue-driven cracks, orientation is generally normal to the predominant stress field
• However, CF cracks are more likely to form branches that follow grain boundaries in the metal
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Corrosion Fatigue in LWRs
• Fatigue is a major consideration where the components are subjected to a very large number of cycles (e.g., high–cycle fatigue) and the primary concern is the endurance limit, i.e., the stress that can be applied an infinite number of times without failure
• Cyclic loadings on a LWR component occurs because of
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 9
changes in mechanical and thermal loadings♦ Number of cycles applied during the design life of an LWR
seldom exceeds 105 and is low–cycle fatigue
• Main difference between high–cycle and low–cycle fatigue is that the former involves little or no plastic strain, whereas the latter involves strains in excess of the yield strain
♦ Design curves for low–cycle fatigue are based on tests in which strain rather than stress is the controlled variable
NUREG-6909, 2/07
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Corrosion Fatigue
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
Fatigue Mechanism
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Corrosion Fatigue
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 11
• Mechanism• LWR Case Study Examples
♦ BWR feedwater nozzle♦ BWR steam dryer support bracket♦ Hamaoka 5 ABWR condenser recirc cap♦ PWR RCP upper seal cavity pressure sensing
line socket weld
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Some NRC Corrosion Fatigue Documents
• BL-88-02 - Rapidly Propagating Fatigue Cracks in Steam Generator Tubes
• BL-79-13 - Cracking in Feedwater System Piping
• BL-79-13 Rev. 2 - Cracking in Feedwater System Piping
• IN98045 - Cavitation Erosion of Letdown Line Orifices Resulting in Fatigue Cracking of Pipe Welds
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
• IN93020 - Thermal Fatigue Cracking of Feedwater Piping to Steam Generators
PRS-11-037 F BMG/ 12
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Some Corrosion Fatigue History
• World War I – failure of steel wire towing ropes attached to paravane equipment (torpedo-shaped underwater devices with serrated teeth) designed to sever mine moorings
• Tried higher tensile strength wire – no improvement• Galvanized original tensile strength wire – worked• This was a corrosion problem, not a strength problem
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Cable failures
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Recommended Corrosion Fatigue Film
No Highwayin the Sky
1951 - Jimmy Stewart and Marlene Dietrich
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 14
• Based on Nevil Shute’s novel No Highway
• 1st aircraft disaster film!
• 1953 – Crash of world's first passenger jet (de Havilland Comet) due to corrosion fatigue
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World Wide Worries OverCorrosion Fatigue!
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D. H. Comet 106
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D. H. Comet 106 Corrosion Fatigue
• de Havilland developed/flew the 1st commercial jet aircraft, D. H. Comet 106, in 1949
♦ Several years ahead of rival Boeing
♦ Commercial operations in early 1952
• Comet crashed shortly after takeoff on May 2, 1953
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
♦ 2 crashes in early 1954 forced British authorities to ground the entire fleet
• Tested fuselage submerged in a tank of water and repeatedly pressurized and depressurized to represent repeated flight cycles
♦ >>1000s cycles, CF cracks were found to be spreading from the square edges of the windows in the passenger cabin
PRS-11-037 F BMG/ 17
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Relationships among SCC, CF and Fatigue
SCC CF Fatigue
Cyclic Stress
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Environment
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Corrosion Fatigue
• Reduction of fatigue resistance due to the presence of a corrosive medium
• Mechanical fatigue resistance values are nearly independent of stress-cycle frequency – allows accelerated testing
• Corrosion fatigue is greatly dependent by stress-cycle
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 19
g g y p y yfrequency – need time for corrosion reactions –disallows accelerated testing
♦ High cycle fatigue crack growth is not strongly influenced by environmental effects
♦ Low cycle fatigue crack growth is a strong function of environment
• Corrosion fatigue cracks are typically transgranular (through the grains) not along gbs. Fracture surfaces may have striations and oxide particles.
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Corrosion Fatigue
Fatigue crack advance occurs by a reversed slip mechanism and the resulting beach marks and striations are often visible
Fatigue data (initiation and growth) is cycles-based, but environmental effects
Beach Marks
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 20
but environmental effects are time-dependent.Thus, problems often occur at low frequency or strain rate.
Cracks are often TG, butif cycling is “gentle,” can be IG
P. Andresen, NRC, 7/06
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Corrosion Fatigue Striations with Corrosion Products
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Corrosion Fatigue - Spatula
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Corrosion Fatigue
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Corrosion Fatigue - MGB Door
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 23
Nice paint!
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Fatigue and Corrosion Fatigue S-N Curves
sFatigue or
Endurance Limit Mechanical Fatigue
What would the results of a fatigue test in a vacuum look like?
Initiation Data
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 24
104 105 106 107
Str
es
Number of Cycles to Failure
Corrosion Fatigue
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Sample Mechanical TheoreticalFatigue S-N Diagram
70
80
90
100si
le S
tres
s
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 25
30
40
50
60
1.0.E+00 1.0.E+01 1.0.E+02 1.0.E+03 1.0.E+04 1.0.E+05 1.0.E+06 1.0.E+07 1.0.E+08
% U
ltim
ate
Tes
Cycles
Endurance limit
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Fatigue and Corrosion Fatigue of Steel
800
1000
1200
mit
, MP
a
Theoretical 50%
Polished
Notched
Corrosion
UTS = ultimate tensile strength
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 26
0
200
400
600
200 400 600 800 1000 1200 1400 1600 1800 2000 2200
En
du
ran
ce L
im
UTS, MPa
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S-N Fatigue Curve for Type 304 SS
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 27
ASME
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εa- N HWC CF of Type 304 SS
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NUREG-6909, 2/07
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Fatigue Monitoring
Pressurizer
SG #1
Pump Pump
Pump No. 1B
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 29
Pump No. 2B
Reactor Pressure Vessel
SG #2No. 1A No. 2A
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FatiguePro®
• EPRI licensed software
• Tracks transients (cycles) and fatigue usage for Class 1 components
♦ Automated cycle counting (ACC) = counts and categorizes plant transients into design basis transients based on raw plant instrument data
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
♦ Computes fatigue usage
° Stress-based fatigue (SBF) = computes CF based on stress histories determined from raw plant instrument data
° Cycle-based fatigue (CBF) = computes CF based on design stress report algorithms and counted plant cycles
• Rapidly evaluates plant transients
PRS-11-037 F BMG/ 30
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BWR Feedwater Nozzle Cracking
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
Nozzle Cracking
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BWR Feedwater Nozzle Cracking
Late 1970s – early 1980s
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NRC as Generic Activity A-10, “BWR Nozzle Cracking.” Interim guidance was provided in NUREG-0312, which specified augmented inspections for the nozzle assembly.
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Cross Section of BWR Feedwater Nozzle
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Cause of BWR Feedwater NozzleCorrosion Fatigue Cracking
• High frequency thermal cycling occurring along the nozzle bore and inner blend radius regions
• Source of the thermal cycling was the mixing of relatively cold feedwater (177-204°C [350-400°F]) with hot reactor water (288°C [550°F]) on the surface of the nozzle inner bore
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 34
• The mixing resulted from leakage of the feedwater into the annulus region through the gap existing between the loose-fitting end of the thermal sleeve and the nozzle safe end
• Cracks initiated in cladding by high cycle CF• Propagation into LAS by low cycle CF - pressure and
thermal cycles from start-up/shutdowns and feedwater on-off transients
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Corrosion Fatigue of BWR RPV Feedwater Nozzle Blend Radius
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Photomacrograph Photomicrograph Photomicrograph Unetched Etched
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Corrosion Fatigue Striationsin a Feedwater Nozzle
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Mitigation of BWR RPV Feedwater Nozzle Cracking
• Remove nozzle stainless steel cladding
• Installation of a modified sparger/thermal sleeve arrangement that eliminated the loose fit at the thermal sleeve/safe end interface
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 37
interface
• Changes to operating procedures and/or feedwater system modifications
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BWR Triple Thermal SleeveFeedwater Nozzle Design
(Low Alloy Steel)
(Carbon Steel)
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(Alloy 600)Alloy 600
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Temperature variations w/woBypass Leakage
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Steam Dryer Support Bracket
C
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
Cracking
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Susquehanna 1 Steam Dryer Support Bracket
• BWR 4 – February 1985 – 1st refueling outage –184º SDSB
• Cracks located through the entire Alloy 600 bracket
• Cause of cracking was CF. Severe wear found
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 41
Cause o c ac g as C Se e e ea ou don other brackets.
• Bracket was replaced in 1985, using the same design as the original
• 1985 analysis and subsequent vibration testing failed to identify source of the fatigue loading that caused the CF and severe wear
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Susquehanna 1 Steam Dryer Support Bracket
Alloy 600
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 42
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Susquehanna 1 Steam Dryer Support Bracket
Alloy 182 Weld Pad
Low RPV
Type 308/309 cladding
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 43
Alloy 600
Low Alloy Steel RPV
CF Crack
Fillet Weld
Full penetration double bevel weld
RPV
Alloy 182
Type 308/309 cladding
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Corrosion Fatigue of Susquehanna 1 Steam Dryer Support Bracket
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 44
Photomicrograph - Transgranular Cracking - Unetched
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Corrosion Fatigue of Susquehanna 1Steam Dryer Support Bracket
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 45
Transgranular crackingNo gross plastic deformation
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Corrosion Fatigue of Susquehanna 1Steam Dryer Support Bracket Metallography
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 46
SEM of fracture face near crack tipTransgranular with fatigue striationsSpacing 1 to 4 μm
300x 1000x
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Cofrentes Steam Dryer Support Bracket
• BWR 6 – November 1991 - 146º SDSB
• Crack was located on the inboard top corner of the Type 304 SS bracket
• Most probable cause of cracking was CF from an unknown alternating load, no evidence of SCC
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 47
• Removed segment (to eliminate loose part concern) showed no evidence of gross plastic deformation
• Planar crack surface apparently resulting from propagation of a crack from a single initiation site
• Plant operators elected to continue operation without any further repair or modification
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Cofrentes Steam Dryer Support Brackets
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 48
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Kuo Sheng 1 Steam Dryer Support Bracket
• BWR 6 – October 2001 - 34 and 214º SDSB
• Cracks located on the inboard corner of the Type 304 SS bracket where there were signs of contact with the bottom of the steam dryer support ring
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 49
• Most probable cause of cracking was CF
• Cracked sections removed to prevent loose parts concern
• Based on good Cofrentes experience, plant operators elected to continue operation without any further repair or modification
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Kuo Sheng 1 Steam Dryer Support Bracket
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 50
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Nine Mile Point 1 Steam DryerSupport Bracket
• BWR 2 – March 2011 - 50º, 131º and 230º SDSB• 50° 1-587A Type 304 SS
♦ Left side bottom 25.8 mm (1.015”) raps around the bottom left corner of bracket for 52.8 mm (2.081”)
♦ Center bottom 22.2 mm (0.875”)
• 130° 1-587B Type 304 SS
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 51
yp♦ 8.9 mm (0.35”) raps around top right corner of bracket
extending down right side for 82 mm (3.23”)♦ 63.5 mm (2.5“) bottom indication in the base material
across the entire lug
• 230º 1-587C Type 304 SS♦ Right side/bracket top 83 mm (3.25”) and transverses
around the top right corner, continues 24 mm (0.93”)
• Most probable cause of cracking is EAC
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Schematic of NMP-1 Steam Dryer Support Bracket Configuration
63.5 mm
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 52
127 mm50.8 mm
mm
203 mm
12.7 mm
63.5 mm
(Collar)
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Nine Mile Point 1 Steam DryerSupport Bracket Design
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 53
(COLLAR)
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NMP- 1 Steam Dryer Support Bracket50º (1-587A) – Left Side Bottom
63.5 mm
Type 304
Type 304
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 54
Alloy 182
Saddle
Alloy 182
52.8 mm
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NMP- 1 Steam Dryer Support Bracket50º (1-587A) – Bracket Center Bottom
22.2 mm 1.8 mmType 304
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 55
Bottom of Alloy 182 Weld
SaddleSaddle
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NMP- 1 Steam Dryer Support Bracket 231º (1-587C) – Right Side
Type 304
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 56
Bracket Side
83 mm
83 mm
Bracket Top
Type 304
Type 304
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NMP- 1 Steam Dryer Support Bracket 231º (1-587C) – Bracket Top
Type 304
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 57
24 mm
127 mm
Type 304
Alloy 182
Alloy 182
Alloy 182
Type 304
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Hamaoka 5 ABWR CF
• Damage to 43 Ti condenser tubes in a turbine steam condenser
• May 14, 2011 ~5 tons of seawater entered reactor following the discovery of ~400 tons of seawater in the condenser, which cools steam
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
seawater in the condenser, which cools steam from the turbine♦ All LPRMs fail a la Millstone 1 in 1972
• 530 tons/h of seawater were flowing through the recirculation pipe
• Corrosion fatigue of weld on recirc pipe cap?
PRS-11-037 F BMG/ 58
Mainichi Daily News, 6/28/11
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Hamaoka 5 ABWR Damage
21,000 Ti tubes
3 cm Ø
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 59
20 cm3.5 kg
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Susquehanna 2 New Steam Dryer
• 15th refuel and inspection outage
• First cycle of 100%inspection for NEW dryer♦ New dryer was installed to “do the right
thing,” i.e., old dryer was OK
• Major indications:
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
Major indications:♦ Dryer seismic ring lug A - through-wall
indication in skirt panel ~ 115 mm (4.5”)
♦ Dryer lug LL-B 140⁰ - Crack-like indication on dryer lower bracket to lifting lug weld 13 mm (~0.5”)
PRS-11-037 F BMG/ 60
E. Camacho, BWRVIP, 6/11
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Susquehanna 2 New Steam Dryer
Indication running through the dryer skirt panel to mid ring 0⁰ weld (th h ll)
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 61
(through-wall)
E. Camacho, BWRVIP, 6/11
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Susquehanna 2 New Steam Dryer
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 62
E. Camacho, BWRVIP, 6/11
Multiple IGSCC indications (4 areas) in dryer skirt weld 135⁰Most prominent cracks are 13 mm (0.5”)- shallow depth
4 indication areas
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RCP Upper Seal Cavity Pressure
Sensing Line Socket
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
Sensing Line Socket Weld Failure
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RCP Socket Weld Failure
• RCS pressure boundary leakage
• 19 mm (¾”) flange to pipe socket weld
• Schedule 160, Type 304 SS pressure
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 64
304 SS pressure sensing line
• First field flange connection off seal package
• NOT = 54ºC (130ºF)• NOP = 5.5 MPa (800
psig)
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Close Up of Leak
Environment:
• 837 ppb Cl!
• 626 ppb SO4!
• 27 ppb F
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 65
• Nominal values all <50 ppb
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RCP Socket Weld Failure
• At OD surface, crack located entirely within weld metal
• Crack extended ~120o around
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 66
~120o around circumference
• No gross plastic deformation evident
120º
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RCP Socket Weld Failure
Circumferential crack
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RCP Socket Weld Failure
• Radial section opposite fracture
• Good quality weld
• Weld dimensions exceeded Code requirements
Pipe
Weld
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 68
requirements
• No evidence of inadequate pull-back
Socket base metal Close up next slide
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RCP Socket Weld Failure
• Multiple, minimally branched cracks in weld metal and pipe
• Transgranular crack path in Type 304 SS pipe base material
Weld
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 69
pipe base material• No evidence of
sensitization• No cracking observed
in Type 316 SS flange base metal
Pipe
Flange
Stress concentration
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RCP Socket Weld Failure
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 70
Striations evident on portions of leak path fracture surface
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RCP Socket Weld Failure
• Observations suggest:♦ Environmentally assisted cracking
♦ Causative loads are cyclic in nature
♦ Stagnant, oxygenated RCS likely a key factor
S i lif t f il h i i
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 71
♦ Service life suggest failure mechanism is age related
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Introduction to Stress Corrosion
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
Cracking
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The Poetry of SCC
The image of stress corrosion I seeIs that of a huge unwanted tree,Against whose trunk we chop and chop,But which outgrows the chips that drop;
At intervals researches gather,And on mechanisms all palaver;Each to his own work will refer,Ignoring those who don’t concur.
On Stress Corrosion (Abridged Version)
S. P. Rideout, Savannah River Laboratory
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 73
And from each gash made in its barkA new branch grows to make more darkThe shade of ignorance around its base,Where scientists toil with puzzled face.
Chemists and metallographers,Technicians and philosophers,Through struggling individuallyTheir common goal: to fell the tree
But as we speculate and ponder,Those who run the mills out yonderTo us with anxious voices wail,“Please help us lengthen ‘time to fail!’”
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Stress Corrosion Cracking
• Ultimate in localized corrosion!• Cracks that create the impression of inherent
brittleness, but it is corrosion!• Bulk alloy retains its typical ductility values• All alloys are susceptible to SCC in at least one
environment Pure metals are very resistant
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 74
environment. Pure metals are very resistant.• SCC does not occur in all environments• An environment that induces SCC in one alloy
does not necessarily induce SCC in another alloy• Environmentally specific cracking (unlike most
corrosion fatigue)• Complex since SCC involves many technical
disciplines, variables and interdependencies
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BWR Example of SCC Mitigationwith Pure Metals
• Pellet cladding interaction (PCI)
• SCC due to corrosive fission products and cladding tensile stress from pellet expansion
• Solution: pure Zr barrier interior cladding by co-extrusion with Zircaloy-2
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 75
Zircaloy-2
Fuel Pellet
Fuel Pellet
Zr
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SCC in LWRs
• SCC is the most virulent of degradation processes in LWRs and is likely to continue
• SCC is not easily detected
• SCC affects the integrity of the most critical components
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
components
• SCC is a precursor to subsequently dangerous although low probability phenomena♦ Break before leak (BBL), not LBB
♦ Loss of coolant accident (LOCA)
PRS-11-037 F BMG/ 76
R. Staehle, QMN, 6/10
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SCC Mechanism
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
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Stress Corrosion Cracking
• There are three necessary fundamental parameters that must be simultaneouslypresent for SCC:
♦ Tensile stress (total of all stresses, i.e., applied, residual etc )
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 78
residual, etc.)♦ “Corrosive” environment♦ Susceptible material
• If anyone of these three necessary fundamental parameters is absent or reduced below some “threshold” value, SCC cannot occur
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Tensile Test
• Most fundamental type of mechanical properties test
• Tensile tests determine how the material will react to forces being applied in tension, i.e., its strength and elongation (ductility) via a stress strain plot
♦ Initially the relationship between the applied load and the elongation is linear
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
and the elongation is linear° “Hooke's Law" where the ratio of stress (σ) to strain (ε) is
a constant E (Young’s Modulus), σ/ε = E
♦ Yield strength (YS) = stress applied to the material at which plastic deformation starts to occur
♦ Since departure from the linear elastic region is not easily identified, the ASTM E8 0.2% offset method is used to determine the offset YS (proof stress)
PRS-11-037 F BMG/ 79
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Engineering Stress Strain CurveS
tres
s (σ
)
0.2% Offset Line Ultimate Tensile
Strength Fracture StrengthStrain
Hardening Necking
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En
gin
eeri
ng
S
Engineering Strain (ε)
Offset Yield Strength
Uniform Elastic Deformation
Uniform Plastic Deformation
Non-uniform Plastic
Deformation (Necking)
Fracture
Tensile Specimens
Proportionality limit
0.2%
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Engineering Stress Strain CurveClose Up
Proportionality limit
Offset Yield Strength
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Young’s Modulus E = σ/ε
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Engineering vs. “True”Stress Strain Curves
s (σ
) Fracture Strength
Engineeringσe = P/A0
εe = (L-L0)/L0
“True”
“True” Stress Strain
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 82
Str
ess
Strain (ε)
σt = P/Aεt =
= ln(L/L0)
Engineering Stress Strain /
Lf
LodL L∫
Engineering stress and engineering strain are calculated based on the original dimensions of the specimen and not the instantaneous values as is the case for “true” stress and strain
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Tensile Testing Equipment
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Resistance heated
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Example of Tensile Test Results
As-received copper specimen
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Post-tensile test copper specimen
Necking
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Cup Cone Fracture Surface - Aluminum
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Cup Cone
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Ductile vs. SCC Failures
Ductile Failures
• High % reduction in area (necking)
• High % elongation
• Dimpled fracture surface
A0
A
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 86
SCC
• ~0% reduction in area
• ~0% elongation
• IG/TG fracture surface
A0
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Ductile vs. SCC Failures
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NUREG-6892, 1/06
Wow!
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SCC Fundamental Parameters
Tensile Stress
Susceptible Material
SCC
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“Corrosive” Environment
Venn Diagram
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Some SCC History – “Caustic Embrittlement”
• 19th and 20th
century riveted carbon steel steam boilers explode
• Cracks around rivet holes
ca 1850
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rivet holes
• Susceptible areas cold worked by riveting
• NaOH from chemical treatment of boiler water – Caustic SCC
• Due to local deposition of concentrated OH- at 200 to 250oC
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Some SCC History – “Remember the Maine!”
1898 Remember the SCC!
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1st war started by SCC!
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SCC Parameters and Mitigationfor “Caustic Embrittlement”
High residualtensile stress from riveting
Carbon steel
SCC
Change the alloy
Anneal out residual
stress/cold work after
riveting
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High temperature water with NaOH
Replace NaOH in coolant or add Na2HPO4
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Some SCC History – “Season Cracking”
• British colonial times in India (1920s)
• Small arms brass cartridges developed small cracks
• Shells would misfire, explode
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• Cracking occurred only during the monsoon season – high RH, high ambient temperatures
• Ammunition stored in horse stables
SCC
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SCC Parameters and Mitigationfor Brass Cartridges in India
High residualtensile
stress from drawing
Cartridge Brass
SCC
Change the alloy (add 1% Si)
Anneal out residual
stress/cold work after drawing
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Warm, high humidity and horse urine!
(NH3)
Remove the ammo from stables
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A Few Examples of Alloy-Environmental Systems Exhibiting SCC
Alloy EnvironmentCarbon Steel Hot nitrite, hydroxide and carbonate
/bicarbonate solutions
High strength steels Water with H2S
Austenitic stainless steels
Chloride solutions; chloride -contaminated steam oxygenated high
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steels contaminated steam, oxygenated high temperature water
High nickel alloys High purity steam, LWR environments
α Brass Ammonia solutions
Aluminum alloys Aqueous Cl-, Br - and I- solutions
Titanium alloys Aqueous Cl-, Br - and I- solutions; organic liquids; N2O4 (dinitrogentetroxide)
This list never gets smaller!
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Anodic Polarization Curvewith SCC Zones
Noble
Passive
Pitting
SCC Potential Zones
Transpassive
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ActiveCurrent Density log | i |, A/cm2
Passive
Active
Zones
Po
ten
tial
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Stress Corrosion Cracking
• SCC propagates in two modes:♦ Intergranular – IGSCC – between the grains (e.g., BWR
IGSCC, IASCC, PWSCC)
♦ Transgranular – TGSCC – across the grains (e.g, Cl SCC)
♦ Can be mixed mode, i.e., IGSCC + TGSCC
C ki i t i ll di l t th t il t
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• Cracking is typically perpendicular to the tensile stress
• Increasing the tensile stress decreases the time to crack initiation and increases the crack propagation rate
• Tensile stresses include applied, residual, thermal and even corrosion product
• Higher the yield stress, the higher the crack growth rate
• Total t failure = t initiation + t propagation
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Microstructures of IGSCC,TGSCC and IDSCC
TGSCC IGSCC IDSCC
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Effect of Tensile Stress on SCCInitiation and Propagation
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Alloy 600 Alloy 82
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Effect of Yield Stress/Cold Work on Crack Growth Rate of Stainless Steel
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T. Kamada, Kansai, 7/07
1 N/mm2 = 1 MPa =0.145 ksi
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Perspective on SCC Initiation
• Initiation data is essential to large systems like SG tubing SCC
• Large, complex components, long operation, welding defects, surface inclusions and damage, etc. “conspire” to make the assumption that initiation is the limiting factor
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
assumption that initiation is the limiting factor uncertain and non-conservative
• Few initiation tests are well-designed due to a lack of:
♦ Sufficient number of specimens♦ Continuous monitoring♦ Surface area and representative conditions
PRS-11-037 F BMG/ 100
P. Andresen, Beaune SCC Initiation Conf., 9/08
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Perspective on SCC Initiation (continued)
• Initiation is typically single-point data:♦ 1 data point per initiation test vs. ~106 data
points per crack growth test
• On-the-fly environmental/stress changes are not possible
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
p
• Often use arbitrary/severe conditions with reverse bending, high stresses/strains, graphite wool crevices, severe surface treatments
PRS-11-037 F BMG/ 101
P. Andresen, Beaune SCC Initiation Conf., 9/08
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Definition of Crack Initiation
• What are the crack dimensions or characteristics associated with “crack initiation”?
♦ Complete failure? (Includes crack growth!)
♦ Evidence of SCC? (All crack sizes often treated equally)
♦ Post-test destructive exam by metallography or SEM?
♦ Video photo or replicate detectability of cracking?
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
♦ Video, photo or replicate detectability of cracking?
♦ In-situ monitoring detectability crack depth vs. time?
♦ Electrochemical noise monitoring for incipient cracking?
♦ Eddy current, UT, acoustic emission indications?
♦ Development of “long” crack mechanics or chemistry?
♦ Development of crack of arbitrary dimension (e.g., grain size)?
PRS-11-037 F BMG/ 102
P. Andresen, Beaune SCC Initiation Conf., 9/08
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Origins of Crack Initiation
• Phenomena responsible for crack initiation can be many:
♦ Purely mechanical cracking from straining of hardened layers
♦ Intergranular corrosion
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
♦ Selective oxidation of grain boundaries during heat treatment
♦ Pitting corrosion
PRS-11-037 F BMG/ 103
P. Andresen, Beaune SCC Initiation Conf., 9/08
Mature chemistry forms in crack of depth ~50 μm (2 mils)Early growth controlled by crack coalescence
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Crack Growth and Crack Initiation
• Continuum in crack initiation and growth:♦ Most factors that accelerate CGR, accelerate initiation
(e.g., CW, temperature, potential, sensitization, stress)
♦ When growth rates decreases to ~10-8 mm/s (12 mpy), initiation is rare
♦ Exceptions may be particularly noteworthy (e g initiation
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
♦ Exceptions may be particularly noteworthy (e.g., initiation is much easier in sensitized SS than CW SS in BWRs)
• Advantages of CGR measurements♦ ~5000 data/hr, 3000-9000 hrs/test vs. 1 initiation data point
♦ On-the-fly evaluation of impurities, potential, temp, K, pH
♦ Precision measurement vs. absence of any on-line detection of “initiation” in most experiments
PRS-11-037 F BMG/ 104
P. Andresen, Beaune SCC Initiation Conf., 9/08
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SCC Initiation vs. Growth
• Calculations show that for a typical 20 mm thick component:
♦ 50% of life is used in growing to 0.01% depth (0.02 mm)
30% lif i d t t 1% d th (0 2 )
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 105
♦ 30% more life is used to grow to 1% depth (0.2 mm)
♦ Depending on detectability, 10 - 20% of life is actual “growth”
P. Andresen, RIP, Corrosion 2001
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Overall Initiation andPropagation Process
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R. Staehle, QMN, 6/10
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Examples of SCC
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SCC of an Aluminum Aircraft Component
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Corrosion Doctors
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IGSCC of Type 416 Stainless Steel
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Palisades service water pump shaft coupling IGSCC due to poor heat treatment, i.e., hardness exceeded limit
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TGSCC in Annealed BWR CRD Line
19 mm (¾ in.) annealed Type 304 SS CRD withdraw lines with surface Cl- contamination operating at 138-288°C (280-550°F)
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Caused by PVC-containing Dymo™ tape crevice (1998)
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St. Lucie Air Receiver Tank Cracking
Th h d f thi
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The head of this tank was formed from a flat plate! No annealing after cold deformation!Marine atmosphere SCC.
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Testing for SCC Initiation and
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Growth
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Constant Displacement Specimens
• Bent beams (BBs), creviced bent beam (CBB), U-bends, reverse U-bends (RUBs), etc.
• Stresses and strains are typically unrealistically high
• Crack initiation process is sensitive to:
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 113
Crack initiation process is sensitive to:♦ Surface oxides
♦ Surface finish
• Suffer load loss upon heating due to modulus changes ♦ Alloy 600 stress relation of >75% from thermal
creep can occur
EPRI, 1011202, 10/04
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Constant Displacement SCCInitiation Test Specimens
C Ring
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C Ring
Bent Beam
U-bend
Double U-bend
U-bend
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Creviced Bent Beam Test
Graphite Wool
Loading Bolts
Graphite wool may have >ppm levels of impuritiesvs. tests with SS-foil crevices with rare failures
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Test Specimen Retaining clips
and screws
H. Offer, et al., 13th Env. Deg., 2007
Considered an “extreme” initiation test
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Westinghouse Bent Beams
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Areva Four Point Bent Beams
Three springs to maintain the stresses during test
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P. Scott, Cold Work Workshop, 6/07
41
2 3
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Reverse U-bend Specimen
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Rack of RUB Specimens
Pre-test
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Pre-test
Post-test
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O-ring Specimen
T C C TT
CT = tensionC = compression
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p
1st crack initiation
2nd crack initiation
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Actively Loaded Specimen Tests
• Pressurized tube
• Constant load
• Constant extension rate test (CERT)/slow strain rate test (SSRT)
C t t i (CT) d l d
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• Compact tension (CT) or wedge open load (WOL) fracture mechanics specimens
• Double cantilever beam (DCB) fracture mechanics specimens
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In-reactor Biaxial TestingPressurized Tube Specimen
Pinch-off pressure seal
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Test Material
Possible Crevice
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Laboratory Constant Load Testing
System uses internal pressure to actively load specimens - on failure, indicator ball drops and is detected
Regenerative
Gas In
Gas Out/Bleed
Rupture DiscAssembly
PressureRecorder
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Manifolds
Type 347Test Vessel
Thermocouple
SectionAA
RegenerativeHeat ExchangerA A
Constant LoadTest Modules
Solution make-upBall Processing
Devices
Insulated Jacket
StripHeaters
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CERT/SSRT
Identical Tests
CERT = constant extension rate test
TensileSpecimen
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SSRT = slow strain rate test
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Alloy 600 and 718 Tensile Specimens
N. Totsuka, et al., Scripta Met., Vol. 20, No. 7, 1986
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J. Deleume, et al., Env. Deg., 2007
All dimensions in mm
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Welded Pipe Tensile Specimen
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Effect of Strain Rate on SCC
Alloy 600 360ºC500 ppm B + 2 ppm Li
30.8 cc/kg (2.75 ppm) H2
1 x 10-7 /s
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5 x 10-7 /s
The higher the strain rate, the less SCC!!
N. Totsuka, paper 04679, Corrosion 2004
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Relationship between Strain Rate and PWSCC
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N. Totsuka, et al., Corrosion, Vol. 61, No.3, 2005
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SCC Crack Growth Test Specimens
12.78 mm12.70 mm
Dia. (2 holes)
30o
<0.076 mm R <0.003 inch R
60.
96 m
m
2.40
inch
13.
97
mm
0.55
inch
3.175 mm0.125 inch
0.503 inch0.500 inch
Fatigue precrack, then intergranular
SCC precrack
Compact Tension (CT)
or
Wedge–Open-Load (WOL) Specimen
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9.65 mm
0.38 inch50.8 mm
2.00 inch
63.5 mm
2.50 inch
30.
48
mm
1.20
inch
double cantileverbeam specimen
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Old WOL Compliance Technique
Specimen transducer mounted on the WOL that spans the crack
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Compliance opening displacement
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CERT/SSRT vs. DCPD
CERT DCPD
X
X = deepest IG crack
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Machined slot
Fatigue pre-crack
IGSCC pre-crack Test
IGSCC
X
X/t = CGR!Remaining ligament
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Good and Bad CT Crack Fronts
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Bad Bad
Good
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Crack Growth Measurement Techniques
• Crack growth rate is commonly obtained by two methods:
♦ Reversing DC potential drop (DCPD) technique using compact tension (CT), wedge-open-load (WOL) or double cantilever beam (DCB) fracture mechanics specimens
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved. PRS-11-037 F BMG/ 133
♦ Constant extension rate test (CERT) (a.k.a. slow strain rate test [SSRT]) using simple tensile specimens
• DCPD technique is the only legitimate CGR technique!
• CERT CRG tests are quick, cheap and very inaccurate!
• CERT is OK for crack initiation, but not for CGR
• Beware of CERT/SSRT generated CGRs!
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Common CT Specimen Orientations
Loading Direction
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L = longitudinalS = shortT = transverse
Crack Growth
Direction
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Examples of CT Specimen Orientations
Areva Heat 93510
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Various CT Orientations Mid-Wall CT Specimen C-L Orientation
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Example of Composite CT Specimens
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Specimen designed to evaluate SCC CGR that initiated inAlloy 182 and propagated into A533 low alloy steel
K. Kumagai, et al., 14th Env. Deg, 2009
EB = electron
beam
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Reversing DC Potential Drop Technique
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In-reactor Reversing DCPD CGR
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W. Wiesenack, PSI NES, 1/07
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Example of Reversing DCPD CGR
SCC#2a - c280 - 690, 41%RA, WN415 CRDM
10.99
10.995
11
11.005
mm
0
0.2
0.4
ote
nti
al,
Vsh
e
Outlet conductivity x0.01
1108h
0.0
01 H
z@
581h
3 x 10-9
mm/s
.7,
0.0
01 H
zold
@ 1
854h
9
0.0
01 H
zd @
3320h
~0 mm/s
Alloy 690 P. Andresen, et al. 13th Env. Deg., 2007
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10.965
10.97
10.975
10.98
10.985
500 1000 1500 2000 2500 3000 3500 4000
Test Time, hours
Cra
ck le
ng
th, m
-1
-0.8
-0.6
-0.4
-0.2
Co
nd
uc
tiv
ity
, μS
/cm
or
Po
CT potentialPt potential
Con
stan
t K
@
c280 - 0.5TCT of 690 + 41%RA, 340C25 ksi√in, 550 B / 1.1 Li, 18 cc/kg H2
To R
=0.7
, 0
+ 9
000s
hold
~5 x 10-10 mm/s
At 340C, pH = 7.60. At 300C, pH = 6.93 and potential would be ~155 mV higher
6.2 x 10-9
mm/s
To R
=0
+ 9
000s
ho
4.3 x 10-9
mm/s
To R
=0.7
, + 8
5,4
00s
hold
1 x 10-9 mm/s = 1.24 mpy
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Stress vs. Stress Intensity Tutorial
• Stress, σ, = load (P)/cross sectional area (A) = P/A• Designers usually use load and stress as design
parameters for comparison with yield strength, σy
• Load is also used in fracture mechanics evaluations, but the parameter is stress intensity factor, K1, rather than σ
• K1 (Mode 1) relates the magnitude of stress at the tip of a
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1 ( ode ) e ates t e ag tude o st ess at t e t p o acrack or flaw to the global stress state of a component
K1 = Gσ √(πa)where G = geometry factor
a = crack length/depth
• All legitimate LWR CGR data is related to K1
• Units of K1 are ksi√in or MPa√m (1 ksi√in ≈ 1.1 MPa√m)• Reference: “Fracture Mechanics in the Nuclear Power
Industry,” EPRI NP-5792-SR, Rev 1. May 1991
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Stress Intensity Factor, K1
• K is used in fracture mechanics to more accurately predict the stress state (“stress intensity”) near the tip of a crack caused by a remote load or residual stresses
• When this stress state becomes critical a small crack grows (“extends”) and the material can fail
• The load at which this failure occurs is referred to as the
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• The load at which this failure occurs is referred to as the fracture strength
• Experimental fracture strength of solid materials is 10 to 1000 x lower than the theoretical strength values since tiny internal or external surface cracks create higher stresses near these cracks
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Stress Intensity Factor, K1 (continued)
• Exposure time needed to cause SCC failure depends on the stress intensity at any pre-existing or developing crack tip
• Stress concentration at the crack tip or flaw can be quantified in terms of K1
• It determines the crack growth rate of SCC for a specific
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• It determines the crack growth rate of SCC for a specific alloy/environment combination
• Catastrophic failure of a component will occur when K1
reaches a critical value, i.e., the fracture toughness of the material, K1C
• Enables the determination of allowable defect size in design to avoid failure under given loading conditions
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Three Basic Modes of Crack Surface Displacements
Y
Y
X
X
Z
Mode 1
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Y
X
X
Z
Z
Mode 2
Mode 3
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Stress Intensity Factor, K1 (continued)
• Below a “threshold” value of K1, i.e., K1SCC, SCC crack growth is not expected
• Stage 1 - Above this value the initial SCC growth rate increases with increasing K1
• Stage 2 - crack growth rate is independent of K1 and depends instead on the environment and temperature
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p p♦ During Stage 2 growth, K1 continues to increase and leads
to the rapid acceleration of the crack, i.e., Stage 3
• Final fast fracture occurs when K1 reaches K1C, which is the fracture toughness of the material
• The higher the value of K1SCC under given conditions, the greater the SCC resistance
• However, many alloys do not appear to have a “threshold” K1SCC
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Growth Rate of SCC Cracks
Stage 1
h R
ate
Stage 2 Stage 3
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Stress Intensity, K1
Cra
ck G
row
t
SCC growth rate depends on environment Fracture
Toughness
K1SCC K1C
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Effect of K on Crack Velocity in Zn and Zn-free PWR Environments
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H. Kawamura, paper 141, Corrosion 98
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Sudden Failure of Alloy 182with Increasing K
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P. Andresen, 13th Env. Deg., 2007
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IGSCC in LWRs
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
IGSCC in BWRs
PWSCC in PWRs
IASCC in LWRs
follow in the next three class segments
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BWRs and PWRs Have a Lot in Common
• Increasingly sophisticated measurement techniques and patient observation have eroded the historical concepts of immunity and thresholds to SCC in high temperature water
• Tendency to compartmentalize LWR SCC into unique modes with individualized mechanisms and d d i H
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
dependencies. However: ♦ CGR data reveal that all SSs and Ni alloys are SCC
susceptible in LWR water whether the water has:° High or low DO or DH° High purity or buffered or contaminated° Higher or lower temperatures
♦ Crack tips are deaerated and at low corrosion potential in both BWRs and PWRs, thus, crack advances under similar conditions
PRS-11-037 F BMG/ 149
P. Andresen and G. Was, ICC, 10/08
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BWR and PWRWater Chemistry Differences
• Coordinated changes vs. time in the B and Li level in PWR primary water that increases the pH at temperature in pure water from 5.62 (BWR) to ~7.2 (PWR)
• H2 concentration from ~40 to 3000 ppb H2
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
• Temperature (274°C BWR vs. 288/323/343°C for the PWR core inlet, core outlet and pressurizer)
• Of these differentiating factors, temperature is the most important in stainless steels, whereas for Ni alloys, both temperature and DH are important
PRS-11-037 F BMG/ 150
P. Andresen and G. Was, ICC, 10/08
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IGSCC Dominates FailureProcess in LWR Components
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• Stainless steels and Ni-base alloys have shown increasing numbers of failures in both BWRs and PWRs due to IGSCC
• Most pressing concerns are currently PWR vessel penetrations (nozzles and weldments) and BWR/PWR core internals
S. Bruemmer, 2005
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CF and SCC Introduction Summary
• Corrosion fatigue is environmentally-assisted cracking (EAC) due to cyclic stresses♦ Not environment specific
♦ Mitigated by design, materials and environmental changes
Corrosion and Corrosion Control in LWRs© 2011 by SIA, Inc. All rights reserved.
g
• SCC is EAC due to nearly constant stress♦ Environment specific
♦ Mitigated by addressing the 3 fundamental parameters for SCC
♦ Dominant corrosion concern in LWRs!
PRS-11-037 F BMG/ 152