Intergranular fracture of fast reactor irradiated stainless steel

Journal Article · Wed Jan 01 00:00:00 EST 1992 · Acta Metallurgica; (United States)

DOI:https://doi.org/10.1016/0956-7151(92)90204-R· OSTI ID:7239054

Ford, I J ^[1]

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1. Theoretical Studies Dept., Materials and Manufacturing Technology Div., AEA Industrial Technology, Harwell Lab., Didcot, Oxon OX11 0RA (GB)

A mechanistic understanding of the failure of fuel pins in a Fast Reactor, in normal operation or in accident conditions, is very important in assessing safety. Progress in gaining such an understanding has been slow and greater emphasis has been placed on empirical failure rules. This paper presents a simple set of physical models describing the intergranular fracture of Fast Reactor irradiated stainless steel fuel pin cladding. The approach emphasizes the importance of both the nucleation and growth of intergranular cavities as well as the effects of helium bubble formation during irradiation. The models allow a unified theoretical approach to be taken in describing unirradiated, in-pile and post-irradiation creep rupture experiments, as well as Fuel Cladding Transient Tests (FCTT).

• OSTI ID: 7239054
• Journal Information: Acta Metallurgica; (United States), Vol. 40:1; ISSN 0001-6160
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
36 MATERIALS SCIENCE
FAST REACTORS
FUEL PINS
FAILURE MODE ANALYSIS
REACTOR COMPONENTS
SAFETY ANALYSIS
STAINLESS STEELS
PHYSICAL RADIATION EFFECTS
CREEP
FRACTURE MECHANICS
FUEL-CLADDING INTERACTIONS
INTERGRANULAR CORROSION
IRRADIATION
REACTOR SAFETY EXPERIMENTS
ALLOYS
CHEMICAL REACTIONS
CORROSION
EPITHERMAL REACTORS
FUEL ELEMENTS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
MECHANICAL PROPERTIES
MECHANICS
RADIATION EFFECTS
REACTORS
STEELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
220900* - Nuclear Reactor Technology- Reactor Safety
360105 - Metals & Alloys- Corrosion & Erosion
360103 - Metals & Alloys- Mechanical Properties