Double-ended break probability estimate for the 304 stainless steel main circulation piping of a production reactor

Conference · Tue Dec 31 04:00:00 EST 1991

OSTI ID:10129878

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

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

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 growing 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.

• Research Organization: Westinghouse Savannah River Co., Aiken, SC (United States)
• Sponsoring Organization: USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 10129878
• Report Number(s): WSRC-MS--91-170; CONF-9108145--2; ON: DE92009414
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220600
36 MATERIALS SCIENCE
360105
CORROSION AND EROSION
CRACKS
HEAT AFFECTED ZONE
PIPES
PRIMARY COOLANT CIRCUITS
PROBABILITY
PRODUCTION REACTORS
RESEARCH
TEST
TRAINING
PRODUCTION
IRRADIATION
MATERIALS TESTING REACTORS
SAVANNAH RIVER PLANT
STAINLESS STEEL-304
STRESS CORROSION
WELDED JOINTS