1 / 31

Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

ULTRASONIC INSPECTION OF THE NOZZLES OF CONTROL RODS AND WELD IN REACTOR CORE AREA OF PRESSURE VESSEL OF LOVIISA NPP (VVER440 ). Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland Bernhard Elsing, Fortum Power and Heat, Loviisa Power Plant, Finland.

justis
Download Presentation

Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript


  1. ULTRASONIC INSPECTION OF THE NOZZLES OF CONTROL RODS AND WELD IN REACTOR CORE AREA OF PRESSURE VESSEL OF LOVIISA NPP (VVER440) Pentti Kauppinen, Harri Jeskanen, VTT, Finland Raimo Paussu, Fortum Nuclear Services, Finland Bernhard Elsing, Fortum Power and Heat, Loviisa Power Plant, Finland

  2. Control rod penetrations to the closure head • Target of the inspection • Structure of the nozzles • Ultrasonic technique applied • Performance of measurement • Results

  3. Upper part of the RPV closure head with control rod housings

  4. Target of the inspection • The target of the inspection is to assure that water has not penetrated in the narrow gap between the ferritic nozzle penetration tube and the inner corrosion protection tube • Water can lead to corrosion of the ferritic tube and corrosion products can cause the bulging of inner tube → the operation of control rods is disturbed • The upper weld inside the penetration nozzle is the susceptible area for leakage

  5. Control rod nozzles: flange between the ferritic penetration tube and austenitic control rod housing

  6. The structure of the control rod penetration nozzle

  7. The structure of the control rod penetration nozzle

  8. Transducer 0° ferritic plate 15 mm Water gap austenitic plate 3.3 mm Principle of the ultrasonic inspection technique • Test arrangement for laboratory simulations

  9. Ultrasonic signals from simulation test and real inspection • Test with 0.6 mm water gap (above) • Result from real inspection; water gap 0.75 mm • Echo on the left is the bottom echo from 15 mm thick nozzle and the echo on the right its multiple • Measurement is based on the interface echoes (in the gates) • The width of the gap is calculated based on the distance between the two interface echoes and on the sound velocities in steel and water

  10. At certain frequencies the amplitude drops and the gain setting of the UT-device has to adjusted properly for reliable detection Calculation made for 0.2 mm water gap; first drop of amplitude at 3.7 MHz 5 MHz transducer was selected for measurements Dependence of the interface echo amplitude from the ultrasonic frequency used in inspection

  11. Performance of inspection: Access to the nozzles

  12. Access to the nozzles

  13. Access to the control rod nozzles

  14. Performance of inspection; access to the nozzles

  15. Measurement signals on the screen of UT-equipment

  16. Opening of a defect detected in the upper weld

  17. Defects on the surface of the corrosion protection tube

  18. Linear crack in the corrosion protection tube

  19. Conclusions from inspections performed • Based on the measurements performed at Loviisa in 2004-2006 two leaking nozzles were detected • In both cases the reason for leakage was a manufacturing defect in the upper weld of the corrosion protection tube • The location of the leakage point could only be detected by helium-test • The sealing weld at the lower end of the tube has been inspected by eddy current testing and no defects have been found • The reliability of the inspection is decreased because the measurement of all nozzles can’t be performed along the whole circumference • In order to have access to the lower part of the nozzle the heat insulation material on the cover should be removed

  20. Inspection of the weld in reactor core area (weld 4) • The target of the inspection is to assure that the outer surface of the reactor pressure vessel shell is free from defects • The soundness of outside surface is especially important in possible emergency cooling situation due to the irradiation embrittlement of the reactor pressure vessel material • Thermal shocks in emergency cooling situation might lead to growth of cracks existing on the outer surface of the shell

  21. 7 6 5 Reactor core area 4 3 2 Weld 1 Reactor pressure vessel of VVER440

  22. Volume A-B-C-D from the outer surface of RPV Volume E-F-H-G from the inner surface of RPV Inspection volumes of weld 4 of RPV shell

  23. The transducer packages used for inspection of inner (left) and outer (right) surface of RPV

  24. Telescope mast and the transducers

  25. Telescope mast used in the inspection

  26. Qualification of the technique; detection of 3 implanted defects in a test block. Defect depths 8 , 5 and 3 mm

  27. Qualification of the technique with test block

  28. Inspection technique applied • For inspection of outer surface area a 70° transmitter-receiver L-wave, 2 MHz probe is used • The sound beam of the transducer is directed just below the surface in order to detect even very low defects opening to the surface • For detection of surface opening defects the creeping waves created on the surface

  29. D- and B-images of indications recorded in the inservice inspections in 2006 (above) and 1999 (below)

  30. Indications on the surface and in the volume of RPV

  31. Conclusions • The two techniques presented have been developed to complete the basic inservice inspections performed according to ASMEXI • The feed-back from RPV inspections performed has been good; the reproducibility of results between different years has been excellent • The opening and repair of control rod nozzles based on the inspection results have verified the conclusions made from UT results • The inspection of control rod nozzles has certain limitations that should be overcome to improve the overall reliability of the method

More Related