Application of a unified deformation-rate law to stress relaxation of AISI Type 316 stainless steel. [LMFBR]

Conference · Sat Jan 01 00:00:00 EST 1983

OSTI ID:5866928

DiMelfi, R J

A unified deformation rate law is presented and its use at describing stress-relaxation in cladding material is examined. An equation is derived based on the classical theory of rate processes for type 316 stainless steel (the reference fuel-cladding material). In this framework, a strain-rate law is evolved from the concept that plastic deformation is controlled by the rate at which dislocations move past obstacles by thermal activation.

• Research Organization: Argonne National Lab., IL (USA)
• DOE Contract Number: W-31-109-ENG-38
• OSTI ID: 5866928
• Report Number(s): CONF-831047-40; ON: DE83014572
• Resource Relation: Conference: American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
36 MATERIALS SCIENCE
LMFBR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR MATERIALS
THERMAL STRESSES
STRESS RELAXATION
TENSILE PROPERTIES
STAINLESS STEEL-316
DEFORMATION
FUEL CANS
REACTOR SAFETY
STRAINS
ACCIDENTS
ALLOYS
BREEDER REACTORS
CHROMIUM ALLOYS
CHROMIUM STEELS
CHROMIUM-NICKEL STEELS
CORROSION RESISTANT ALLOYS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
IRON ALLOYS
IRON BASE ALLOYS
LIQUID METAL COOLED REACTORS
MATERIALS
MECHANICAL PROPERTIES
MOLYBDENUM ALLOYS
NICKEL ALLOYS
REACTORS
RELAXATION
SAFETY
STAINLESS STEELS
STEELS
STRESSES
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
360103 - Metals & Alloys- Mechanical Properties