Assessment of early, useful, and wear-out operating periods for liquid-metal centrifugal pumps
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:5977554
- Oak Ridge National Lab., TN (United States)
- Power Reactor and Nuclear Fuels Development Corp., Ibaraki (Japan)
The Centralized Reliability Data Organization (CREDO) was founded at the Oak Ridge National Laboratory in 1978 as a data base to support reliability, availability, and maintainability analyses of liquid-metal reactor components. Although {approximately}3,000 items were received or updated in the data base last fiscal year, the primary emphasis of CREDO has changed from data collection to probabilistic risk assessment support, preventive maintenance support, and data analysis. This paper discusses the results of an analysis to determine the early, useful, and wear-out operating periods of liquid-metal centrifugal pumps.
- OSTI ID:
- 5977554
- Report Number(s):
- CONF-910603-; CODEN: TANSA
- Journal Information:
- Transactions of the American Nuclear Society; (United States), Vol. 63; Conference: Annual meeting of the American Nuclear Society (ANS), Orlando, FL (United States), 2-6 Jun 1991; ISSN 0003-018X
- Country of Publication:
- United States
- Language:
- English
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Conference
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· Transactions of the American Nuclear Society; (USA)
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OSTI ID:5977554
An assessment of liquid-metal centrifugal pumps at three fast reactors
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Fri Oct 01 00:00:00 EDT 1993
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OSTI ID:5977554
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Tue Jan 01 00:00:00 EST 1991
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5977554
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LIQUID METAL COOLED REACTORS
PRIMARY COOLANT CIRCUITS
RISK ASSESSMENT
PUMPS
RELIABILITY
AVAILABILITY
DATA BASE MANAGEMENT
DESIGN
FAILURES
MODIFICATIONS
ORNL
PROBABILISTIC ESTIMATION
REACTOR MAINTENANCE
SEALS
SERVICE LIFE
SODIUM
TIME DEPENDENCE
WEAR
ALKALI METALS
COOLING SYSTEMS
ELEMENTS
MAINTENANCE
MANAGEMENT
METALS
NATIONAL ORGANIZATIONS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
LIQUID METAL COOLED REACTORS
PRIMARY COOLANT CIRCUITS
RISK ASSESSMENT
PUMPS
RELIABILITY
AVAILABILITY
DATA BASE MANAGEMENT
DESIGN
FAILURES
MODIFICATIONS
ORNL
PROBABILISTIC ESTIMATION
REACTOR MAINTENANCE
SEALS
SERVICE LIFE
SODIUM
TIME DEPENDENCE
WEAR
ALKALI METALS
COOLING SYSTEMS
ELEMENTS
MAINTENANCE
MANAGEMENT
METALS
NATIONAL ORGANIZATIONS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
US AEC
US DOE
US ERDA
US ORGANIZATIONS
220900* - Nuclear Reactor Technology- Reactor Safety
210500 - Power Reactors
Breeding