Steam generator secondary pH during a steam generator tube rupture
The Nuclear Regulatory Commission requires utilizes to determine the response of a pressurized water reactor to a steam generator tube rupture (SGTR) as part of the safety analysis for the plant. The SGTR analysis includes assumptions regarding the partitioning of iodine between liquid and vapor in steam generator secondary. Experimental studies have determined that the partitioning of iodine in water is very sensitive to the pH. Based on this experimental evidence, the NRC requested the INEL to perform an analytical assessment of secondary coolant system (SCS) pH during an SGTR. Design basis thermal and hydraulic calculations were used together with industry standard chemistry guidelines to determine the SCS chemical concentrations during an SGTR. These were used as input to the Facility for Analysis of Chemical Thermodynamics computer system to calculate the equilibrium pH in the SCS at various discrete time during an SGTR. The results of this analysis indicate that the SCS pH decreases from the initial value of 8.8 to approximately 6.5 by the end of the transient, independent of PWR design.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (United States)
- Sponsoring Organization:
- NRC; Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5375670
- Report Number(s):
- EGG-NE-10046; ON: DE92012219
- Country of Publication:
- United States
- Language:
- English
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BOILERS
C CODES
CHEMICAL ANALYSIS
COMPUTER CALCULATIONS
COMPUTER CODES
COOLING SYSTEMS
ELEMENTS
ENERGY TRANSFER
ENRICHED URANIUM REACTORS
FAILURES
FLUID MECHANICS
HALOGENS
HEAT TRANSFER
HYDRAULICS
IODINE
MECHANICS
NONMETALS
PARTITION
PH VALUE
POWER REACTORS
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTORS
RUPTURES
SAFETY
SECONDARY COOLANT CIRCUITS
STEAM GENERATORS
THERMAL REACTORS
THERMODYNAMICS
TUBES
VAPOR GENERATORS
WATER COOLED REACTORS
WATER MODERATED REACTORS