Perspective on present and future alloy development efforts on austenitic stainless steels for fusion application

Conference · Sun Jan 01 04:00:00 EST 1984

OSTI ID:6179853

Maziasz, P J

The purpose of this paper is to address important questions concerning how to effect further alloy development of austenitic stainless steels for resistance, and to what extent the behavior of other properties under irradiation, such as strength/embrittlement, fatigue/irradiation creep, corrosion (under irradiation), and radiation-induced activation must be influenced. To summarize current understanding, helium has been found to have major effects on swelling and embrittlement, but several metallurgical avenues are available for significant improvement relative to type 316 stainless steel. Studies on fatigue and irradiation creep, particularly including helium effects, are preliminary but have yet to reveal engineering problems requiring additional alloy development remedies. The effects of irradiation on corrosion behavior are unknown, but higher alloy nickel contents make thermal corrosion in lithium worse. 67 refs. (JDB)

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6179853
• Report Number(s): CONF-841246-30; ON: DE86004808
• Country of Publication: United States
• Language: English

Related Subjects

36 MATERIALS SCIENCE
360103 -- Metals & Alloys-- Mechanical Properties
360106* -- Metals & Alloys-- Radiation Effects
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700209 -- Fusion Power Plant Technology-- Component Development & Materials Testing
ALLOYS
AUSTENITIC STEELS
CHEMICAL REACTIONS
CORROSION
CREEP
EMBRITTLEMENT
FATIGUE
HYDROGEN EMBRITTLEMENT
IRON ALLOYS
IRON BASE ALLOYS
IRRADIATION
MATERIALS
MECHANICAL PROPERTIES
NEUTRON FLUENCE
PHYSICAL RADIATION EFFECTS
RADIATION EFFECTS
STEELS
SWELLING
THERMONUCLEAR REACTOR MATERIALS
THERMONUCLEAR REACTOR WALLS
TITANIUM ALLOYS