Comparison of inelastic response of Type 316 stainless steel and HT-9 materials on the fusion reactor first wall
Journal Article
·
· Fusion Technol.; (United States)
OSTI ID:6197771
An analysis based on available materials property data has been performed to compare the inelastic response of first-wall structural materials. The first wall is assumed to be operated under the conditions of the pulse surface heat load, coolant pressure, and bombardment from energetic particles. An axisymmetric inelastic stress analysis calculates the long-term redistribution of the stress in a thin-walled plate element of a cylindrical module that is subjected to membrane load. The plate is free to expand but is constrained from bending. The redistribution is caused by inelastic deformation from irradiation creep and swelling. The present effort has concentrated on the performance of two candidate structural materials, namely, Type 316 stainless steel and HT-9 ferritic steel. The results obtained indicate a lower cyclic stress and a lower mean stress for the HT-9 ferritic steel than for stainless steel under the conditions of interest. Therefore HT-9 ferritic steel is quite attractive for future application of the fusion reactor first wall.
- Research Organization:
- National Tsing Hua Univ., Nuclear Engineering Dept., Hsinchu
- OSTI ID:
- 6197771
- Journal Information:
- Fusion Technol.; (United States), Journal Name: Fusion Technol.; (United States) Vol. 12:1; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
Similar Records
Lifetime analysis of ferritic steel structures for high temperature fusion applications
Effects of irradiation and high heat flux on the lifetime performance of ferritic and 316 stainless steels
Microstructural evolution of heavy-ion irradiated HT-9 ferritic steel
Conference
·
Mon Jul 01 00:00:00 EDT 1985
· Fusion Technol.; (United States)
·
OSTI ID:5876727
Effects of irradiation and high heat flux on the lifetime performance of ferritic and 316 stainless steels
Thesis/Dissertation
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:6120737
Microstructural evolution of heavy-ion irradiated HT-9 ferritic steel
Conference
·
Sat Dec 31 23:00:00 EST 1988
· Transactions of the American Nuclear Society; (USA)
·
OSTI ID:6502773
Related Subjects
36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOY-HT-9
ALLOYS
AXIAL SYMMETRY
BENDING
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CHROMIUM-NICKEL STEELS
COOLANTS
CORROSION RESISTANT ALLOYS
CREEP
DEFORMATION
FIRST WALL
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEATING LOAD
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MEMBRANES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PARTICLES
PERFORMANCE
PHYSICAL RADIATION EFFECTS
PRESSURE EFFECTS
PULSES
RADIATION EFFECTS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRESS ANALYSIS
SYMMETRY
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
360103 -- Metals & Alloys-- Mechanical Properties
360106 -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700209* -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOY-HT-9
ALLOYS
AXIAL SYMMETRY
BENDING
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-MOLYBDENUM STEELS
CHROMIUM-NICKEL STEELS
COOLANTS
CORROSION RESISTANT ALLOYS
CREEP
DEFORMATION
FIRST WALL
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HEATING LOAD
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
MATERIALS TESTING
MECHANICAL PROPERTIES
MEMBRANES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
PARTICLES
PERFORMANCE
PHYSICAL RADIATION EFFECTS
PRESSURE EFFECTS
PULSES
RADIATION EFFECTS
STAINLESS STEEL-316
STAINLESS STEELS
STEELS
STRESS ANALYSIS
SYMMETRY
TESTING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS