0

Full Content is available to subscribers

Subscribe/Learn More  >

Identification and Resolution of Piping Analysis Activities for Extended Power Uprates at Nuclear Plants

[+] Author Affiliations
Dilip Bhavnani

PSE&G Power LLC, NJ

Paper No. PVP2002-1244, pp. 293-299; 7 pages
doi:10.1115/PVP2002-1244
From:
  • ASME 2002 Pressure Vessels and Piping Conference
  • Pressure Vessel and Piping Codes and Standards
  • Vancouver, BC, Canada, August 5–9, 2002
  • Conference Sponsors: Pressure Vessels and Piping Division
  • ISBN: 0-7918-4650-4
  • Copyright © 2002 by ASME

abstract

Recent experience has shown that many utilities have installed new feedwater flow measurement instrumentation, which is designed with new, proven technology that more accurately monitors feedwater flow and therefore, allows for improved thermal power level calculations. As a result of this new approach, many utilities have been able to extend limited power upgrades to the tune of 1.4%, and yet with no noticeable additional environmental impact. These electric power increases are generally attributable to the large design margins included in the original nuclear power plant designs and in addition, to the technological advances that have been made to the nuclear industry. Power increases are now carried out by several nuclear utilities in the United States with the NRC’s concurrence. Current nuclear power plants are providing cheap, reliable and affordable electricity to help meet current energy growing demands. As a result of this, power uprate increases are encouraged. Current economic conditions strongly favor power uprates and plant life extensions. In the early 1990s, a limited power uprate program was initiated, but due to complex design reviews, this was not steadfastedly recommended during this time period. Nuclear Steam Supply Systems (NSSS) vendors performed a key role in this nuclear power uprate program. This paper discusses structural and piping qualification review required to achieve these power uprate programs, currently being performed by nuclear utilities in the United States.

Copyright © 2002 by ASME

Figures

Tables

Interactive Graphics

Video

Country-Specific Mortality and Growth Failure in Infancy and Yound Children and Association With Material Stature

Use interactive graphics and maps to view and sort country-specific infant and early dhildhood mortality and growth failure data and their association with maternal

NOTE:
Citing articles are presented as examples only. In non-demo SCM6 implementation, integration with CrossRef’s "Cited By" API will populate this tab (http://www.crossref.org/citedby.html).

Some tools below are only available to our subscribers or users with an online account.

Related Content

Customize your page view by dragging and repositioning the boxes below.

Related eBook Content
Topic Collections

Sorry! You do not have access to this content. For assistance or to subscribe, please contact us:

  • TELEPHONE: 1-800-843-2763 (Toll-free in the USA)
  • EMAIL: asmedigitalcollection@asme.org
Sign In