A failure probability estimate of Type 304 stainless steel piping

Conference · Mon Jan 01 04:00:00 EST 1990

OSTI ID:6399168

Daugherty, W L; Awadalla, N G; Sindelar, R L ^[1]; Mehta, H S ^[2]

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1. Westinghouse Savannah River Co., Aiken, SC (USA)
2. General Electric Co., San Jose, CA (USA)

The large break frequency resulting from intergranular stress corrosion cracking in the main circulation piping of the Savannah River Site (SRS) production reactors has been estimated. Four factors are developed to describe the likelihood that a crack exists that is not identified by ultrasonic inspection and that grows to instability prior to becoming through-wall and being detected by the ensuing leakage. The estimated large break frequency is 3.4 {times} 10{sup {minus}8} per reactor year. This result compares favorably to similar estimates made for commercial boiling water reactors. 9 refs., 8 figs.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (USA)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 6399168
• Report Number(s): WSRC-MS-90-38; CONF-9010151--3; ON: DE91004299
• Country of Publication: United States
• Language: English

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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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36 MATERIALS SCIENCE
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ALLOYS
AUSTENITIC STEELS
BWR TYPE REACTORS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
CORROSION
CORROSION RESISTANT ALLOYS
CRACK PROPAGATION
CRACKING
DECOMPOSITION
FAILURE MODE ANALYSIS
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
LEAK TESTING
MATERIALS
NICKEL ALLOYS
PIPES
PYROLYSIS
REACTORS
STAINLESS STEEL-304
STAINLESS STEELS
STEEL-CR19NI10
STEELS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
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THERMOCHEMICAL PROCESSES
WATER COOLED REACTORS
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