Workshop on thermally treated alloy 690 tubes for nuclear steam generators: proceedings
- eds.
The workshop was held to collect available metallurgical and corrosion data on thermally treated (TT) alloy 690 and to compare these data with that for other candidate tube alloys for nuclear steam generators. The data indicate that TT alloy 690 is the most corrosion-resistant tube alloy. It is immune to stress corrosion cracking (SCC) in primary water, chlorides and sulfates. The TT improves its corrosion resistance to caustic, the most corrosive environment. Manufacturing parameters for alloy 690 tubing are little different than for alloy 600 except that higher mill-annealing temperatures are required. Some optimization of annealing parameters and some additional corrosion testing are needed to complete the qualification of alloy 690.
- Research Organization:
- Electric Power Research Inst., Palo Alto, CA (USA); Stone and Webster Engineering Corp., Boston, MA (USA)
- OSTI ID:
- 5409392
- Report Number(s):
- EPRI-NP-4665-S-SR; CONF-8606180-; ON: TI86920431
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220200* -- Nuclear Reactor Technology-- Components & Accessories
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
BOILERS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CORROSION
CRACKING
CRYSTAL STRUCTURE
DECOMPOSITION
INCONEL 690
INCONEL ALLOYS
INSPECTION
MATERIALS
MATERIALS TESTING
MICROSTRUCTURE
NICKEL ALLOYS
NICKEL BASE ALLOYS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PYROLYSIS
REACTOR MATERIALS
STEAM GENERATORS
TESTING
THERMAL POWER PLANTS
THERMOCHEMICAL PROCESSES
TUBES
VAPOR GENERATORS