Published 1992
| Version v1
Report
Open
Principal working group 3 on primary circuit integrity
Description
The main themes of this conference (13 papers) are: operating experience on leakages and failures in nuclear power plant piping, coolant circuits and steam generator tubes, probabilistic estimation and risk assessment, system failure analysis, leakage events and frequency, leak rate models and crack propagation mechanics, damage mechanisms and rupture probability
Availability note (English)
MF available from INIS under the Report Number.Files
28008597.pdf
Files
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Additional details
Publishing Information
- Imprint Pagination
- 189 p.
- Report number
- NEA-CSNI-R--95-6
Conference
- Title
- Workshop on Reactor Coolant System Leakage and Failure Probabilities.
- Dates
- 9-11 Dec 1992.
- Place
- Cologne (Germany).
INIS
- Country of Publication
- Nuclear Energy Agency of the OECD (NEA)
- Country of Input or Organization
- Nuclear Energy Agency of the OECD (NEA)
- INIS RN
- 28008597
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Is Lead record
- Yes
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRACK PROPAGATION; CRACKS; FAILURES; FRACTURE MECHANICS; LEAKS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; STEAM GENERATORS; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- BOILERS; COOLING SYSTEMS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTOR COMPONENTS; SAFETY; SIMULATION; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; VAPOR GENERATORS