A fleet of reactor coolant pump thrust bearings were experiencing loss of oil inventory through a face rubbing mechanical oil seal. In a span of six months, Westinghouse developed a replacement seal which retrofit into the existing bearing, erected a full scale bearing test system, operated the prototype seal through various operating conditions utilizing Six Sigma Design of Experiments methodology, qualified the seal for sustained use in an operating reactor plant and supported the installation of the retrofit seals. The retrofit seal replaced a problematic face rubbing seal with a controlled leakage design utilizing a floating ring — a pressure reducing bushing free to translate in the X-Y plane. The prototype seal system was optimized through use of the Design of Experiments. Design optimization was aimed at reducing oil aeration to levels lower than those present with the original equipment, which when achieved, provided improved heat transfer from the bearing. The test system was constructed around a production thrust bearing, identical to those installed in the plant, which was modified to facilitate collection of a variety of process variables. In all, the system was capable of simultaneously sampling and storing data from 56 separate channels; while recording digital video from eight sources, from cameras both inside and outside of the bearing. All in-service operating parameters were duplicated by the test system, including: computer controlled variable vertical thrust load from zero to 90 tons, computer controlled variable radial thrust load and acceleration from standstill to operating speed in 16 seconds. Safe shutdown operating variables were monitored automatically by the system, in the event of a faulted condition the system automatically detected the fault and initiated a safe shutdown automatically. To date, all installed seal systems have performed as designed; allowing essentially no leakage at this location from the bearing reservoir. The test system continues to be used on development projects focused on improving other aspects of the bearing’s performance.
Skip Nav Destination
16th International Conference on Nuclear Engineering
May 11–15, 2008
Orlando, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4814-0
PROCEEDINGS PAPER
Development of Full Scale Reactor Coolant Pump Thrust Bearing Test System and Qualification Process for Retrofit Thrust Bearing Oil Seal With Commercial Grade Components
Jason Sinkhorn,
Jason Sinkhorn
Westinghouse Electric Company, Madison, PA
Search for other works by this author on:
William Mendez
William Mendez
Westinghouse Electric Company, Madison, PA
Search for other works by this author on:
Jason Sinkhorn
Westinghouse Electric Company, Madison, PA
William Mendez
Westinghouse Electric Company, Madison, PA
Paper No:
ICONE16-48956, pp. 381-384; 4 pages
Published Online:
June 24, 2009
Citation
Sinkhorn, J, & Mendez, W. "Development of Full Scale Reactor Coolant Pump Thrust Bearing Test System and Qualification Process for Retrofit Thrust Bearing Oil Seal With Commercial Grade Components." Proceedings of the 16th International Conference on Nuclear Engineering. Volume 1: Plant Operations, Maintenance, Installations and Life Cycle; Component Reliability and Materials Issues; Advanced Applications of Nuclear Technology; Codes, Standards, Licensing and Regulatory Issues. Orlando, Florida, USA. May 11–15, 2008. pp. 381-384. ASME. https://doi.org/10.1115/ICONE16-48956
Download citation file:
10
Views
Related Proceedings Papers
Related Articles
Application of Digital Computers to Bearing Design
Trans. ASME (October,1957)
Effect of Foil Geometry on the Static Performance of Thrust Foil Bearings
J. Eng. Gas Turbines Power (August,2018)
The Influence of Surface Patterning on the Thermal Properties of Textured Thrust Bearings
J. Tribol (November,2018)
Related Chapters
Hydrodynamic Lubrication
Design of Mechanical Bearings in Cardiac Assist Devices
PSA Level 2 — NPP Ringhals 2 (PSAM-0156)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Insights and Results of the Shutdown PSA for a German SWR 69 Type Reactor (PSAM-0028)
Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)