Structure of PWR primary corrosion products
The composition and structure of crud taken from the fuel elements of various pressurized water reactors (PWR's) were determined by SEM, EDAX, x-ray analysis, infrared spectroscopy, and thermomagnetic analysis. The samples were taken from reactors varying in materials of construction from all stainless steel to mainly Inconel 600 and Zircaloy fuel cladding. It is shown that crud is essentially a nickel ferrite (Ni/sub x/Fe/sub3-x/O/sub 4/) with 0.45 < x < 0.75. Calibration of the lattice parameter versus x allows convenient determination of the main constituents of crud samples. Chromium also enters the inverse spinel lattice substitutionally to give a composition Cr/sub y/Ni/sub x/Fe/sub 3-x-y/O/sub 4/. Aluminum, when present, generally formed amorphous compounds with silicon in the loose crud.
- Research Organization:
- Westinghouse Research and Development Center, Pittsburgh, PA
- OSTI ID:
- 6127188
- Journal Information:
- Corrosion; (United States), Vol. 35:5; Conference: Corrosion/78 meeting, Houston, TX, USA, Mar 1978
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
36 MATERIALS SCIENCE
CHROMIUM OXIDES
LATTICE PARAMETERS
INCONEL 600
CORROSION PRODUCTS
IRON OXIDES
NICKEL OXIDES
PWR TYPE REACTORS
FUEL CANS
STAINLESS STEELS
ZIRCALOY
PRIMARY COOLANT CIRCUITS
ALLOYS
CHALCOGENIDES
CHROMIUM ALLOYS
CHROMIUM COMPOUNDS
COOLING SYSTEMS
CORROSION RESISTANT ALLOYS
INCONEL ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
IRON COMPOUNDS
NICKEL ALLOYS
NICKEL BASE ALLOYS
NICKEL COMPOUNDS
NIOBIUM ALLOYS
OXIDES
OXYGEN COMPOUNDS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
STEELS
TIN ALLOYS
TRANSITION ELEMENT COMPOUNDS
WATER COOLED REACTORS
WATER MODERATED REACTORS
ZIRCONIUM ALLOYS
ZIRCONIUM BASE ALLOYS
210200* - Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
360105 - Metals & Alloys- Corrosion & Erosion
360202 - Ceramics
Cermets
& Refractories- Structure & Phase Studies