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  • Westinghouse In-Core Information Surveillance & Engineering (WINCISE™)

    WINCISE™ is an Operational Support System that uses Westinghouse technology licensed by the NRC to obtain an accurate, continuous core power distribution measurement. Westinghouse developed the WINCISE System as a replacement for the Movable Detector (M/D) System. WINCISE uses an OPARSSEL™ (Optimized...
    Posted to Westinghouse Nuclear (FileGallery) by admin on 05-08-2007
  • Uprating Programs

    Nuclear power plant upratings provide incremental electric generation capacity in a timely and cost-effective manner. Westinghouse has successfully implemented over 70 plant upratings providing over 2900 MWe of additional power generation. Three types of uprating programs are currently available: • Measurement...
    Posted to Westinghouse Nuclear (FileGallery) by admin on 05-08-2007
  • Upper Head Temperature Reduction (UHTR) Program

    Alloy 600 primary water stress corrosion cracking (PWSCC) is very sensitive to temperature. Lowering temperatures can be an effective way to increase the time for crack initiation and reduce the rate of crack propagation, thereby extending the useful life of a reactor vessel head (RVH). The Upper Head...
    Posted to Westinghouse Nuclear (FileGallery) by admin on 05-08-2007
  • Tube Integrity & Alternate Repair Criteria

    Since the early 1980s, Westinghouse has been recognized as the industry leader with regard to engineering analysis of operating steam generator degradation. We've gained experience and developed tools to accurately assess degradation and optimize operational efficiency when degradation mechanisms exist...
    Posted to Westinghouse Nuclear (FileGallery) by admin on 05-08-2007
  • Steam Generator Tube Stabilizer - Tube Damper

    The Westinghouse Steam Generator Tube Stabilizer System evolved from analytical and experimental efforts to effectively stabilize degraded steam generator tubes. Because tubes can be susceptible to vibration, the Tube Stabilizer System was tested to assess its effectiveness, characterize the vibration...
    Posted to Westinghouse Nuclear (FileGallery) by admin on 05-08-2007
  • Simplified Head Assembly (SHA)

    Reactor head assembly and re-assembly activities are major considerations when it comes to the refueling outage critical path schedule, personnel radiation exposure, critical containment resources, personnel safety, and cost. The Westinghouse integrated head package (IHP) is an enhanced equipment design...
    Posted to Westinghouse Nuclear (FileGallery) by admin on 05-08-2007
  • Replacement Steam Generator (RSG) Feedring Design

    Primary drivers for steam generator replacement include a utility's desire to reduce or eliminate maintenance costs due to Alloy 600 issues, uprate power, and realize operational benefits associated with advances in steam generator design. A number of plants have already made the decision to replace...
    Posted to Westinghouse Nuclear (FileGallery) by admin on 05-08-2007
  • Replacement Steam Generator (RSG) Axial Flow Preheater (AXP) Design

    Primary drivers for steam generator replacement include a utility's desire to reduce or eliminate maintenance costs due to Alloy 600 issues, uprate power, and realize operational benefits associated with advances in steam generator design. A number of plants have already made the decision to replace...
    Posted to Westinghouse Nuclear (FileGallery) by admin on 05-08-2007
  • Replacement Pressurizer

    The primary driver for pressurizer replacement is a plant's desire to reduce or eliminate downtime due to pressurizer heater sleeve leaks or other Alloy 600 leaks that have plagued the industry for some time. A number of plants have already made the decision to replace their pressurizers; others are...
    Posted to Westinghouse Nuclear (FileGallery) by admin on 05-08-2007
  • Reactor Vessel Closure Head Replacement

    In response to industry events involving Alloy 600 material in reactor vessel closure head (RVCH) penetrations, a number of pressurized water reactor (PWR) utilities have, or intend to, replace the RVCH. In addition to the potential for eliminating material issues associated with Alloy 600, the RVCH...
    Posted to Westinghouse Nuclear (FileGallery) by admin on 05-08-2007
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