Secondary water condition entering the SG

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Discussion Overview

The discussion focuses on the properties of secondary water entering the steam generator of a pressurized water reactor (PWR). Participants explore various aspects including thermodynamic properties, chemical purity, and relevant system parameters.

Discussion Character

  • Technical explanation
  • Exploratory

Main Points Raised

  • One participant inquires about the properties of secondary water entering the steam generator, specifically seeking information on its thermodynamic characteristics.
  • Another participant provides detailed parameters for feedwater, including its state as a compressed liquid, enthalpy, temperature, and the influence of heat recovery from turbine condensate.
  • Specific data points are shared, such as feedwater temperature (446ºF or 230ºC) and steam flow rates for different reactor designs, including EPR and AP1000.
  • A participant notes the importance of water purity in the secondary system, highlighting historical issues with corrosion in the 1970s and suggesting resources on PWR secondary chemistry.
  • Several participants express appreciation for the shared links and information, indicating that the resources are helpful for their understanding.

Areas of Agreement / Disagreement

Participants generally agree on the importance of thermodynamic properties and water purity in the context of secondary water in PWRs, but no consensus is reached on specific values or implications of these properties.

Contextual Notes

Limitations include the lack of specific definitions for terms like "subcooling" and "enthalpy," as well as the dependence on various operational conditions that may affect the properties discussed.

Who May Find This Useful

This discussion may be useful for students and professionals in nuclear engineering, materials science, and those interested in the operational characteristics of pressurized water reactors.

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Hi, I am a student specializing in material, now i would like to stimulate secondary water of a Pressurized water reactor, could anybody tell me the water property entering the Steam Generator?

Thanks!
 
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The feedwater is a compressed liquid and its subcooling or enthalpy/temperature depend on how much reheat (heat recovered) from the condensate of the high and low pressure turbines (through heat recovery heat exchangers).

See - Condensate-Feedwater Systems
http://www.nucleartourist.com/systems/fw.htm

Search for feedwater in this document (Components are listed by temperatures are not given):
http://www.nrc.gov/reading-rm/basic-ref/teachers/04.pdf

EPR Secondary Side Parameters - http://www.ne.doe.gov/pdffiles/eprttsuseprmechsysa.pdf
Code:
•Outlet Steam Static Pressure   1118 psia(77.1 bar)
•Secondary Design Pressure      1450 psia
•Steam Flowrate                     1407.4 lbm/s (638.4 kg/s)
•Feedwater Temperature          446ºF (230ºC)
•Overall Circulation Ratio           3.6
•Water Mass                          85.1 Tons (77.2 Metric Tons)
•Steam Mass                          6.06 Tons (5.50 Metric Tons)
•Total Mass                           91.2 Tons (82.7 Metric Tons)

For AP1000 - http://www.nrc.gov/reactors/new-reactors/design-cert/ap1000/dcd/Tier%202/Chapter%205/5-1_r15.pdf (Table 5.1-2, page 5.1-10)

Feedwater temperature, °F 440
Exit steam pressure, psia 836
Steam flow, lb/hr per steam generator 7.49x106
Total steam flow, lb/hr 14.97x106
 
Last edited:
specializing in material

Thermodynamic properties as Astronuc said.

Cemically - purity of the water is incredible, to parts per billion.
Search on PWR Secondary Chemistry turns up plenty of articles. Corrosion was a huge problem in 1970's.
 
Astronuc said:
...

Some great links again Astronuc. Thanks a lot!
 
Thank you so much! That great link helps me a lot!
 

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