repair of the nru reactor vessel - iaea...lesson learned david s. cox atomic energy of canada...
TRANSCRIPT
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Repair of the NRU
Reactor Vessel:
Technical Challenges and
Lesson Learned
David S. Cox
Atomic Energy of Canada Limited
Chalk River Laboratories
International Conference on Research Reactors:
Safe Management and Effective Utilization
2011 November
Rabat, Morocco
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Chalk River Laboratories
• The NRU Reactor
• Leak location and condition assessment
• Inspection tool development
• Determination of degradation mechanism
• Development of repair methods
• Execution of weld repair
• Lessons Learned
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NRU - National Research Universal
• First operation 1957 November
• 200 MW design; current licence limit 135 MW
• Large, versatile research reactor
–R&D support of CANDU® reactor fuel & materials irradiation
–National Research Council Canadian Neutron Beam Centre
• Medical & industrial isotopes
–Benefits more than 76,000 people
internationally each day
–Used for cancer treatment and early
cancer detection, diagnosis of
heart conditions, circulatory system
& other organs
–Mo-99, I-125, I-131, Xe-133, Co-60,
Ir-192
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• NRU obtained full WANO membership in late 2010
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Cross Section of NRU
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Heavy Water Leak- 2009 May 14
Upper Deck
Plate
Permanent
Guide Tubes
Calandria
Vessel
Lower
HeaderLeak Site
Vessel
Wall
J-Rod
Annulus
Water
Reflector
Wall
Upper Deck
Plate
Permanent
Guide Tubes
Calandria
Vessel
Lower
HeaderLeak Site
Vessel
Wall
J-Rod
Annulus
Water
Reflector
Wall
Reaching the leak site: • Leak site is 9 m below the deck plate
at the base of the vessel
• Access through 12 cm dia. tubes
• High radiation environment
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Vessel wall:
8 mm 5052
aluminum
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Visual Inspections in 2009 May
• Minor heavy water leak from the vessel into the
surrounding annulus detected (~5 kg/h)
–Visual inspection determined that the leak site was
in the vessel wall at the bottom of the annulus
–Determined that the heavy water leak was due to
corrosion of the reactor vessel wall from the outside
–Additional areas of corrosion around the base of the
vessel also required remediation
–Decision made to remain shutdown for an extended
period to repair the vessel
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Leak Site
• Detailed non-destructive
examination of lower
vessel wall performed
–Leak location
determined
accurately
–Widespread
corrosion identified
in the lower portion
of the J-rod annulus
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Reactor
vessel wall Reflector
wall
Water box
Light water
gutter
Lip
Heavy water
gutter
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9
A Closer Look at the Leak Site
Annulus
floor
Vessel
wall
Vessel
wall
Annulus
floor
Area of leak
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Condition Assessment of Vessel
Non-destructive examination: • Remote video inspections
• Ultra-sound examination
• Eddy current probes
• Over two million inspection results
• Four phases
One of largest single NDE
inspection campaigns ever
carried out in the nuclear industry.
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Inspection Tools
Mk-I Mk-II
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Phases I & II – Inspection Probes
Phased Array UT
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Hi-Resolution ET
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Mk II Inspection Tool in Mock-Up
8 full-height mockups utilized through outage
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Inspection Teams
Mk I deployment Mk II deployment
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NRU Annulus Cross-Section
Vessel Wall
Wall-to-Flange Weld
Lip Annulus Floor
Bottom Flange
Gutter Baffle Block
Bottom Plate
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Map of Vessel Wall Thickness
16
BR-29/30 Test Weld BR-45
JR-13/17 JR-18
JR-41 JR-30 JR-28 JR-25/27 JR-23 JR-21
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Locations to Repair
10 Repair Areas 1. BR-45
2. BR-29/30
3. JR-30
4. JR-28
5. JR-21
6. JR-41
7. JR-18
8. JR-23
9. JR-25/27
10.JR-13/17
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Tooling to Clean Vessel Wall
Cleaning of the vessel wall:
• Critical step in welding process
• Removal of gibbsite layer from
vessel
• Articulating vacuum to recover
debris
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Mechanical Cleaning Tool
Tool Head
Delivery Tool Body
Deployment Mechanism
Actuation/ Control Dive
Cups
Deck Plate Quick Disconnect
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Cleaning Tool Deployment Arm
Primary carriage
Secondary carriage
Deployment linkage
Deployment arm
Pneumatically operated
tool head
Silicon Carbide
Brush
Thick walled SS tube (Delivery Tool Body)
•Arm has 965 mm horizontal reach
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JR-41 Leak Site After Cleaning
In-Vessel Cleaning completed for all repairs sites and material
sampling locations
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Obtaining Samples of the Vessel Wall
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Scoop Samples
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Welding on Irradiated Material
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Coupon Cutting at Leak Site
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Corrosion Coupon
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Coupon Removed from Vessel Wall
• J-rod Side Heavy Water side
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Corrosion Mechanism
• J-rod annulus designed to be filled with carbon dioxide
gas and kept dry
• However:
–Aging of CO2 system reduced gas flow
–Light water ingress from reflector leaks into J-rod annulus
–Air ingress from openings in J-rod annulus
–High radiation environment
• Created the conditions for radiolytic production of nitric
acid
• General wastage corrosion in wetted regions, and
localized corrosion at air/water interface
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Articulating J-Rod
Annulus Vacuum Tool
Near JR-3 position
After
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Cleaning the Annulus
Before
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Welding Challenges
1. Geometry: 9 m remote through 12 cm diameter
openings, reaching around obstructions in vessel
2. Vessel distortion from heat
3. High radiation fields on tooling
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Liburdi Welding & Support Tool Set
1. Horizontal weld tool
2. Vertical Weld Tool
3. Horizontal Cleaning & Repair Tool
4. Vertical Cleaning and Repair Tool
5. Patch Deployment Tool
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Liburdi Weld Delivery System
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Liburdi Weld Delivery System
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Welding Control Interface
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Vertical Welding Tool
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Weld Design Process
Engineering
Weld
Development
NDE
Structural
FEA
Weld Stress
Analysis #1
Weld Stress
Analysis #2 Weld Map
Crack Examination
Surface/HAZ
Thickness
Lack of Fusion
Volumetric
Fillets/Groove Welds
Vertical Welds
Horizontal Welds
Fillet/Groove Welds
Window Frames
Plates
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Qualification of the Welding
Cross
Sections
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Test Weld (with Scoop)
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Summary of Repair Areas
Site
Weld
Area
(cm2)
Lowest
Elevation
Weld/Plate
(mm)
Min. Wall
Thickness
(mm)
Welding Operations
H/- V
Buildup
(mm)
Backing
Strips/
Structural
Plates
Plate
Build-
up
2nd
Layer
BR-45 45.4 18 7 V-3 N N N
BR-29/30 90.2 18 7 V-3 N N N
JR-30 139.6 25 4 V-3 N N N
JR-28 106.2 65 4 V-3 N N N
JR-21 347.7 15 3 H-3 N N N
JR-41 153.9 0/15 4 H-3 1-BS Y N
JR-18 83.2 25 4 H-3 0 N N
JR-23 433.6 2/35 1-2 H&V-2.5 2-BS 3 mm Y
JR-25/27 619.1 37/60 0-1 H&V-3.0 4-SP N N
JR-13/17 1250.6 5/25 0-1 H&V-4.0
H 3.0
9-SP N N
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Weld Repair
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Repair at JR-41 – The Leak Site
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Backing
strip
placement
Backing
strip
welding
Final Weld Overlay
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Final Repair – JR-13/17
Challenges: • Two through wall
penetrations
• Thinning to less
than 1mm
• Located below and
between two re-
entrant cans
• Large area: W x H
59 cm x 26 cm
10.4” x 23”
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Challenges - Final Repair
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Challenges - Final Repair
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Weld Process Map – JR-13/17
45
Patching
Tacking
Verticals
Horizontals
4mm Overlay
3mm Overlay
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Weld Stress Analysis
Prediction of loading on vessel seal, and displacement
of vessel wall, in response to weld stresses
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Repair at JR-13/17
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Multiple challenges encountered:
• Plate attachment
• Design change
• Crack repair and re-inspection
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Other Parallel Outage Work
• System Refurbishment Program
–Heavy Water System major maintenance &
inspections
–Process Water maintenance & inspections
–Moderator change (66 Mg heavy water)
– 26 Ci/L replaced with ~ 2.5 Ci/L
–Fuelling Machine major maintenance (Fuel Rod
Flask)
–Installation of seismic supports for loop piping
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2010 August 17 - Return to Service
49
- Commission approval
to refuel past hold
point: 2010 July 5th
- Return to Service and
high power operation,
safely achieved 2010
August 17
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Lessons Learned - Repair
1. Necessary to establish broad design requirements
early for repair tooling and proceed into fab/testing in
absence of final specifications
– Pursued multiple repair methods until final decision made
2. Full size mock-ups that simulated important spatial
constraints for tooling were essential
3. Thermal/mechanical simulations of each weld repair
were necessary to limit plastic strains and protect
vessel seals
4. Practice, practice, practice to establish process control
under conditions in mock-ups that simulate in-vessel
conditions to the extent possible
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Lessons Learned - Continued
5. Close interaction with Regulatory at multiple levels
provided clarity to licensing requirements
– Protocol signed by CNSC and AECL Presidents
– Defined regulatory deliverables and timeline for approvals
– Transparent process brings certainty
6. Important to provide regular communications to Public
and Stakeholders
– Weekly media updates
– Video presentations
– Website
www.NRUCanada.ca
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Key Suppliers to AECL:
• Liburdi Automation
• Promation Nuclear
• Eclipse Scientific
• Equity Engineering
• The Welding Institute
• Goldak & Associates
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Closing Facts
• 40 remote operated tools designed and fabricated for
inspection, sampling, cleaning, repair
• 1 km of weld bead applied
• 3 tonnes of aluminum plate consumed for weld development
and training work (300 plates)
• 4,000 hours of in-vessel inspections
• 2 million NDE inspection results
• 1.8 terabytes of in-vessel video record
• 650 quality surveillance inspections
• 200 reactor assemblies moved/installed
• 73 Stakeholder status updates and 27 information videos
issued to public
• 75,000 unique website visits (www.NRUCanada.ca)
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