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

Conference · Tue Jan 01 04:00:00 EST 1991

OSTI ID:5857055

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

---

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: DOE; USDOE, Washington, DC (United States)
• DOE Contract Number: AC09-89SR18035
• OSTI ID: 5857055
• Report Number(s): WSRC-MS-91-170; CONF-9108145--2; ON: DE92009414
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
220600* -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
36 MATERIALS SCIENCE
360105 -- Metals & Alloys-- Corrosion & Erosion
ALLOYS
AUSTENITIC STEELS
CHEMICAL REACTIONS
CHROMIUM ALLOYS
CHROMIUM-NICKEL STEELS
COOLING SYSTEMS
CORROSION
CORROSION RESISTANT ALLOYS
CRACKS
HEAT AFFECTED ZONE
HEAT RESISTANT MATERIALS
HEAT RESISTING ALLOYS
HIGH ALLOY STEELS
IRON ALLOYS
IRON BASE ALLOYS
JOINTS
MATERIALS
NATIONAL ORGANIZATIONS
NICKEL ALLOYS
PIPES
PRIMARY COOLANT CIRCUITS
PROBABILITY
PRODUCTION REACTORS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
SAVANNAH RIVER PLANT
STAINLESS STEEL-304
STAINLESS STEELS
STEEL-CR19NI10
STEELS
STRESS CORROSION
US AEC
US DOE
US ERDA
US ORGANIZATIONS
WELDED JOINTS
ZONES