Corrosion studies of a stainless steel structure for the ITER (International Thermonuclear Experimental Reactor) aqueous lithium salt blanket concept
The aqueous lithium salt blanket (ALSB) employs water, with a dissolved lithium compound, as both the coolant and tritium breeding medium. The ALSB concept is one of three blanket options currently being examined for breeding tritium in the International Thermonuclear Experimental Reactor (ITER). To provide data and recommendations for materials and chemistry selection relevant to application of the ALSB in ITER, corrosion studies have been initiated, focusing on Type 316 stainless steel in lithium hydroxide and lithium nitrate solutions. This report presents the preliminary results of these corrosion studies. 4 refs., 9 figs., 1 tab.
- Research Organization:
- Rensselaer Polytechnic Inst., Troy, NY (United States)
- Sponsoring Organization:
- DOE/ER
- DOE Contract Number:
- FG02-89ER52161
- OSTI ID:
- 6988152
- Report Number(s):
- DOE/ER/52161-1; ON: DE90009925; TRN: 90-010574
- Country of Publication:
- United States
- Language:
- English
Similar Records
Corrosion studies of a stainless steel structure for the ITER (International Thermonuclear Experimental Reactor) aqueous lithium salt blanket concept
Aqueous corrosion and stress corrosion of 316SS for the ITER water-cooled blanket concept
Effects of cold work on stress corrosion cracking of type 316L stainless steel in hot lithium hydroxide solution
Technical Report
·
Mon Oct 01 00:00:00 EDT 1990
·
OSTI ID:6988152
+2 more
Aqueous corrosion and stress corrosion of 316SS for the ITER water-cooled blanket concept
Technical Report
·
Tue Jan 01 00:00:00 EST 1991
·
OSTI ID:6988152
Effects of cold work on stress corrosion cracking of type 316L stainless steel in hot lithium hydroxide solution
Journal Article
·
Thu Jul 01 00:00:00 EDT 1993
· Corrosion (Houston); (United States)
·
OSTI ID:6988152
Related Subjects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
STAINLESS STEEL-316
CORROSION
BREEDING BLANKETS
CRACKS
ELECTROCHEMICAL CORROSION
ITER TOKAMAK
LITHIUM
MECHANICAL STRUCTURES
PROGRESS REPORT
RADIOLYSIS
STRESS CORROSION
THERMONUCLEAR REACTOR MATERIALS
ALKALI METALS
ALLOYS
AUSTENITIC STEELS
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CLOSED PLASMA DEVICES
CORROSION RESISTANT ALLOYS
DECOMPOSITION
DOCUMENT TYPES
ELEMENTS
HEAT RESIS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
METALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
RADIATION CHEMISTRY
RADIATION EFFECTS
REACTOR COMPONENTS
STAINLESS STEELS
STEEL-CR17NI12MO3
STEELS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700209* - Fusion Power Plant Technology- Component Development & Materials Testing
700201 - Fusion Power Plant Technology- Blanket Engineering
STAINLESS STEEL-316
CORROSION
BREEDING BLANKETS
CRACKS
ELECTROCHEMICAL CORROSION
ITER TOKAMAK
LITHIUM
MECHANICAL STRUCTURES
PROGRESS REPORT
RADIOLYSIS
STRESS CORROSION
THERMONUCLEAR REACTOR MATERIALS
ALKALI METALS
ALLOYS
AUSTENITIC STEELS
CHEMICAL RADIATION EFFECTS
CHEMICAL REACTIONS
CHEMISTRY
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CHROMIUM-NICKEL-MOLYBDENUM STEELS
CLOSED PLASMA DEVICES
CORROSION RESISTANT ALLOYS
DECOMPOSITION
DOCUMENT TYPES
ELEMENTS
HEAT RESIS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MATERIALS
METALS
MOLYBDENUM ALLOYS
NICKEL ALLOYS
RADIATION CHEMISTRY
RADIATION EFFECTS
REACTOR COMPONENTS
STAINLESS STEELS
STEEL-CR17NI12MO3
STEELS
THERMONUCLEAR DEVICES
TOKAMAK DEVICES
700209* - Fusion Power Plant Technology- Component Development & Materials Testing
700201 - Fusion Power Plant Technology- Blanket Engineering