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The document defines the test method for evaluating the corrosion of nuclear fuel cladding tubes within the primary coolant in pressurized water reactors (PWR) nuclear power plants under condition of zinc injection. It details the test principle, the fuction of test equipment, test procedure and the assessment of test result, etc. It specifies the control methods for water chemistry, the internal heat of the cladding tube, heat flux density, and surface void fraction, as well as the post-evaluation of the corrosion hehavior after the corrosion test.
The document is applicable to evaluating the CRUD and CRUD-induced corrosion behaviors on the surface of nuclear fuel cladding tubes in primary coolant with zinc injection for PWR nuclear power plants. The test material includes various types of cladding tubes such as zirconium alloy, Cr-coated zirconium alloy, FeCrAl alloy, etc.
Reģistrācijas numurs (WIID)
91292
Darbības sfēra
The document defines the test method for evaluating the corrosion of nuclear fuel cladding tubes within the primary coolant in pressurized water reactors (PWR) nuclear power plants under condition of zinc injection. It details the test principle, the fuction of test equipment, test procedure and the assessment of test result, etc. It specifies the control methods for water chemistry, the internal heat of the cladding tube, heat flux density, and surface void fraction, as well as the post-evaluation of the corrosion hehavior after the corrosion test.
The document is applicable to evaluating the CRUD and CRUD-induced corrosion behaviors on the surface of nuclear fuel cladding tubes in primary coolant with zinc injection for PWR nuclear power plants. The test material includes various types of cladding tubes such as zirconium alloy, Cr-coated zirconium alloy, FeCrAl alloy, etc.
