Evaluation of exposure conditions for the water-side corrosion test of a sodium heated steam generator evaporator model employing a duplex tube (2160 hours at critical heat flux - phase III SSGM tests). [LMFBR]

Technical Report · Mon Dec 01 04:00:00 EST 1975

DOI:https://doi.org/10.2172/6332265· OSTI ID:6332265

Waszink, R P; Hwang, J Y; Efferding, L E

This report describes the specialized corrosion test water steam loop, test procedures, test conditions, and test results. A complete water chemistry and thermal hydraulic performance history is given and evaluated for the Phase III test program. The movement of the dryout location and the heat flux variations in pre- and post-critical heat flux regions are documented and analyzed. On seven occasions during the course of the test program to date, the operating conditions drifted from the CHF reference Phase III operation in the dryout regime into the DNB regime. The corresponding corrosion mechanism experienced differing exposure conditions on these occasions. CHF sensitivity to this apparent drift behavior is evaluated.

• Research Organization: Westinghouse Electric Corp., Tampa, FL (USA). Tampa Div.
• DOE Contract Number: AC03-76SF00962
• OSTI ID: 6332265
• Report Number(s): WNET-123; ON: DE81026909
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BOILERS
BREEDER REACTORS
CHEMICAL REACTIONS
CHEMISTRY
CORROSION
CRITICAL HEAT FLUX
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT FLUX
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
PERFORMANCE TESTING
REACTORS
STEAM GENERATORS
TEST FACILITIES
TESTING
TUBES
VAPOR GENERATORS
WATER CHEMISTRY