Investigation of pressure transient propagation in pressurized water reactor feedwater lines
Results are reported of a study for the Nuclear Regulatory Commission (NRC) to provide a general understanding of pressure transient (water hammer) propagation in pressurized water reactor (PWR) steam generator feedwater piping systems. A typical feedwater network is defined, and pressure transient initiation is discussed, as well as the plausible pulse shapes reported. The analysis is performed by using the computer codes PTA and WHAM. Forces are calculated at elbows and valves by using momentum principles. The effects of pipe yielding, pipe wall friction, and elbow and value losses are included. Pipe yielding and elbow/valve effects are found to be important, and pressure magnitudes and forces are substantially reduced when these effects are included in the analysis. Typical pressure and force time histories are also given.
- Research Organization:
- California Univ., Livermore (USA). Lawrence Livermore Lab.
- DOE Contract Number:
- W-7405-ENG-48
- OSTI ID:
- 5452084
- Report Number(s):
- UCRL-52265
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
AUXILIARY SYSTEMS
AUXILIARY WATER SYSTEMS
FEEDWATER
HYDROGEN COMPOUNDS
MATHEMATICAL MODELS
OXYGEN COMPOUNDS
PWR TYPE REACTORS
REACTORS
WATER
WATER COOLED REACTORS
WATER HAMMER
WATER MODERATED REACTORS