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© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved.
35th Annual EPRI Steam Generator NDE and Tube Integrity workshop
Clearwater Beach, FL, USA
July 18~20, 2016
K.Namba, T. Hasebe, T.Kinoshita, T. Matsuura, I.Seki
and T. Tsuruta
New and Improved Inspection Techniques
for
Steam Generator Tubes
to
Further Enhance the Safety and Reliability
of
Nuclear Power Plants in Japan
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© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved.
Contents
1
Current situation of nuclear power plants in Japan
Continuous development and improvement of inspection
techniques to enhance safety and reliability
• Multi-functional UT system
• PWSCC depth-sizing using UT techniques
• Improved VT techniques
Conclusions
Page 3
© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved.
Contents
2
Current situation of nuclear power plants in Japan
Continuous development and improvement of inspection
techniques to enhance safety and reliability
• Multi-functional UT system
• PWSCC depth-sizing using UT techniques
• Improved VT techniques
Conclusions
Page 4
© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 3
Timeline after Fukushima accident
After the Fukushima Daiichi Nuclear Accident caused by the Tohoku Earthquake and Tsunami in
March 2011, the nuclear regulatory system in Japan was reorganized. Shown below is a timeline
summary of events and actions relative to the resumption of NPP operations in Japan.
2011 2012 2013 2014 2015 2016
Overall/
Plant
operation
NRA
assessment
MHI activity
Fukushima accident
NRA established
Plant operation stopped one after another
New regulations ordered
NRA review
• Safety analysis• Mid- and long- term preventative measures• Plant design and construction enhancements to prevent severe accidents
12 PWR plants applied to resume operation
Takahama-3 resumed operation
(Takahama-4 postponed to resume operation)
Sendai-1/2 resumed operation
injunction
Pre-operation inspection for Ikata-3
*Nuclear Regulation Authority (NRA)
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Plant situation as of July, 2016
Plant Utility Reactor Status of NRA review/inspection
Sendai-1/2 Kyusyu PWR Review of design enhancements and Pre-operation
inspection completed. Operation resumed.
Takahama-3 Kansai PWR Review of design enhancements and Pre-operation
inspection completed. Operation resumed but
stopped again by District Court order.
Takahama-4 Kansai PWR Review of design enhancements and Pre-operation
inspection completed. Operation is postponed by
District Court order.
Ikata-3 Shikoku PWR Review of design enhancements and Pre-operation
inspection completed. Operation will be resumed in
end of July.
Takahama-1/2 Kansai PWR Review of construction plan completed.
Ohi-3/4 Kansai PWR
Review of application for installment license in
progress.
Mihama-3 Kansai PWR
Genkai-3/4 Kyusyu PWR
Tomari-1/2/3 Hokkaido PWR
PWR plants with applications to resume operation
Genkai-1,Ikata-1 and Mihama-1/2 were decided to be decommissioned.
License renewal over 40 years operation were applied for Takahama-1/2 and
Mihama-3. Takahama-1/2 were already approved.
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© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 5
Plant Utility Reactor Status of NRA review/inspection
Kashiwazaki-6/7 Tokyo BWR
Review of plant design, construction, safety
and reliability for the application of a renewed
operations license, in progress.
Shimane-2 Chugoku BWR
Onagawa-2 Tohoku BWR
Higashidori-1 Tohoku BWR
Hamaoka-3/4 Chubu BWR
Tokai-2 JAPC BWR
Shiga-2 Hokuriku BWR
Oma J-power BWR
Plant situation as of July, 2016 (cont’)
BWR plants with applications to resume operation
Hamaoka-1/2, Tsuruga-1, and Fukushimadaiichi-1/2/3/4/5/6 are to be
decommissioned.
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© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved.
Contents
6
Current situation of nuclear power plants in Japan
Continuous development and improvement of inspection
techniques to enhance safety and reliability
• Multi-functional UT system
• PWSCC depth-sizing using UT techniques
• Improved VT techniques
Conclusions
Page 8
© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 7
Continuous improvement of Inspection Techniques
As a preventative measure against the potential negative effects of service induced tube degradation
(flaws), and to enhance the safety and reliability of steam generators, it is necessary to develop, and
continuously improve, the applied NDE techniques.
The goal is to achieve the earliest detection and characterization possible in support of root cause
analysis and mitigation.
Moreover, it is important to continuously analyze and assess the results from improved NDE techniques
and to apply that knowledge to inform each aspect of plant operations from design, to construction, to
specific operating parameters.
To achieve improvements in detection and characterization the various flaw types, MHI has developed
highly advanced and effective NDE techniques.
Examples of specifically targeted flaws are PWSCC in the tube sheet region or at the TTS, and wall
thinning either in the free span or near/under tube support plates.
The, methods, technologies, and specific techniques that MHI has developed/improved are:
• Multi-functional UT system
• PWSCC depth-sizing using UT techniques
• Improved VT techniques
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Continuous improvement of Inspection Techniques
Summary table of UT and VT
Purpose Method Feature
Wear depth sizing
SCC detection
Multi-functional UT • Detectability: 20%t depth
• Sizing accuracy (wear): 5%t
SCC depth sizing PWSCC depth-sizing UT
• Detectability: 20%t
• Sizing accuracy: approximately
10%t (more than 30%t)
Surface
observation of
SCC
VT• Detectability: 5 to 10μm width
SCC can be detected
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© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved.
Contents
9
Current situation of nuclear power plants in Japan
Continuous development and improvement of inspection
techniques to enhance safety and reliability
• Multi-functional UT system
• PWSCC depth-sizing using UT techniques
• Improved VT techniques
Conclusions
Page 11
© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 10
Multi-functional UT System
Outline of multi-functional UT
Feature
• Detection of outside/inside cracks and wear in straight section locations.
• Simultaneous implementation of straight beam and angle beams techniques.
• Sizing accuracy is enhanced through an algorithm which automatically
compensates for the varying distance of UT sensor to the tube surface as it is
scanned
• Accurate Probe positioning is provided by an accurately controlled probe driver and
built-in ECT coil which identifies landmarks such as tube supports or the TTS.
Sensor for
Axial flaw
Sensor for
Circ. flawStraight UT
sensor for wear
ECT sensor for probe
positioning
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Multi-functional UT System
Detectability and Characterization Accuracy
• Detectability (For SCC and wear): 20%t depth for 7/8in. tube
• Sizing accuracy (For wear): 5%t for 7/8in. tube
ThicknessWall loss
Evaluation
: 22%t
Evaluation result of 20% depth EDM notch
Axial distance[mm]
Circ distance[°]
Tip of defect
Outer surface
B scope Corrected C scope
Line 1 Line 3X
Line No
Tube
Flaw
ID OD
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© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved.
Contents
12
Current situation of nuclear power plants in Japan
Continuous development and improvement of inspection
techniques to enhance safety and reliability
• Multi-functional UT system
• PWSCC depth-sizing using UT techniques
• Improved VT techniques
Conclusions
Page 14
© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 13
PWSCC depth-sizing UT Technique
Sensor for
Circ. flaw
Sensor for
Axial flaw
Feature
• High S/N ratio is achieved by “point focusing” the ultrasonic beam and by reduction
of the echo from tube inner surface.
• Angle beam technique with single element probe is applied and the echo from tip of
defect is used so as to enhance PWSCC detectability from multi functional UT.
Outline of PWSCC depth-sizing UT
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PWSCC depth-sizing UT Technique
Detectability and Characterization Accuracy
• Detectability: 20%t for 7/8in. tube
• Sizing accuracy: approximately RMSE 0.13mm (more than 30%t) for 7/8in. tube
Fig.5 Results of UT sizing
0
20
40
60
80
100
0 20 40 60 80 100 Actual depth (%t)
Evalu
ate
d d
epth
by U
T(
%t)
Axial SCC (CCW)
Axial SCC( CW)
Circ. SCC (DOWN)
Circ. SCC( UP)
C scope D scope
B scope A scope
Axial SCC data within 22%t
Tip echo
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© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved.
Contents
15
Current situation of nuclear power plants in Japan
Continuous development and improvement of inspection
techniques to enhance safety and reliability
• Multi-functional UT system
• PWSCC depth-sizing using UT techniques
• Improved VT techniques
Conclusions
Page 17
© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 16
Improved VT Techniques
Camera head with Lens unit for
viewing ahead
Camera head with Lens unit
for side viewing
Description of VT
Feature
• Camera for both ahead and side viewing
• 360 degree articulation
• Accurate probe positioning with well controlled probe driver and ECT coil
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Improved VT Techniques
3.0
mm
4.0mm
亀裂欠陥多数
Camera image Sketch Replica
Detectability and Characterization Accuracy
• Detectability: 5 to 10μm width SCC can be detected for 7/8in. Tube
• Comparison with previous methods (replica and sketch of it):
approximately equal to previous methods
Superior SCC
Previous methodsVT
Advantage of VT
• ECT pushers and remote controlled positioning robots can be used to apply the
VT probe greatly reducing radiation exposure. • (The alternative, replicating flaws, requires inspectors much higher radiation exposure)
3.0mm
4.0mm
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© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved.
Contents
18
Current situation of nuclear power plants in Japan
Continuous development and improvement of inspection
techniques to enhance safety and reliability
• Multi-functional UT system
• PWSCC depth-sizing using UT techniques
• Improved VT techniques
Conclusions
Page 20
© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 19
Conclusions
• Improved UT technologies and techniques were developed to
achieve more accurate characterization and depth sizing of wear
and SCC type flaws.
• Improved VT technologies and techniques were developed to
achieve far more efficient and effective surface inspections with
superior detection and characterization of SCC, and it greatly
reduces radiation exposure as compared to the alternative.
• These more highly enhanced NDE techniques have now proven
to provide increased sensitivity for early detection while vastly
improving flaw characterization accuracy (i.e. flaw orientation as
well as geometric and depth sizing).
• Enhanced NDE techniques like these further contribute to NPP
safety and reliability by providing higher value input to
continuous condition monitoring and operational assessment
programs (CMOA).
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© 2016 MITSUBISHI HEAVY INDUSTRIES, LTD. All Rights Reserved. 20