Steam generator secondary pH during a steam generator tube rupture
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.
- University of North Texas United States
Enriched Uranium Reactors, 570, Failures, Nonbreeding, Nonboiling Water Cooled, Hydraulics, Ph Value, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Mechanics, Reactor Cooling Systems, Halogens, 220900 -- Nuclear Reactor Technology-- Reactor Safety, 220900, C Codes, Chemical Analysis, Secondary Coolant Circuits, Reactor Components, Light-Water Moderated, Computer Calculations, 22 General Studies Of Nuclear Reactors, Reactor Safety, Tubes, Computer Codes, Pwr Type Reactors, Cooling Systems, Thermal Reactors, Reactors, Elements, Heat Transfer, Steam Generators, Vapor Generators, Nonmetals, Chemical Analysis 210200, Energy Transfer, Power Reactors, Thermodynamics, Water Moderated Reactors 210200* -- Power Reactors, Ruptures, Water Cooled Reactors, Safety, Boilers, Iodine, Partition
Enriched Uranium Reactors, 570, Failures, Nonbreeding, Nonboiling Water Cooled, Hydraulics, Ph Value, Fluid Mechanics, 21 Specific Nuclear Reactors And Associated Plants, Mechanics, Reactor Cooling Systems, Halogens, 220900 -- Nuclear Reactor Technology-- Reactor Safety, 220900, C Codes, Chemical Analysis, Secondary Coolant Circuits, Reactor Components, Light-Water Moderated, Computer Calculations, 22 General Studies Of Nuclear Reactors, Reactor Safety, Tubes, Computer Codes, Pwr Type Reactors, Cooling Systems, Thermal Reactors, Reactors, Elements, Heat Transfer, Steam Generators, Vapor Generators, Nonmetals, Chemical Analysis 210200, Energy Transfer, Power Reactors, Thermodynamics, Water Moderated Reactors 210200* -- Power Reactors, Ruptures, Water Cooled Reactors, Safety, Boilers, Iodine, Partition
selected citations These citations are derived from selected sources.This is an alternative to the "Influence" indicator, which also reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).1 popularity This indicator reflects the "current" impact/attention (the "hype") of an article in the research community at large, based on the underlying citation network.Average influence This indicator reflects the overall/total impact of an article in the research community at large, based on the underlying citation network (diachronically).Average impulse This indicator reflects the initial momentum of an article directly after its publication, based on the underlying citation network.Average
Citations provided by BIP!Popularity provided by BIP!