Published 1992
| Version v1
Report
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Steam generator tubes rupture probability estimation - study of the axially cracked tube case
Creators
- 1. Institut Jozef Stefan, Ljubljana (Slovenia)
- 2. AIB-Vincotte Nucleaire, Brussels (Belgium)
Description
The objective of the present study is to estimate the probability of a steam generator tube rupture due to the unstable propagation of axial through-wall cracks during a hypothetical accident. For this purpose the probabilistic fracture mechanics model was developed taking into account statistical distributions of influencing parameters. A numerical example considering a typical steam generator seriously affected by axial stress corrosion cracking in the roll transition area, is presented; it indicates the change of rupture probability with different assumptions focusing mostly on tubesheet reinforcing factor, crack propagation rate and crack detection probability. 8 refs., 4 figs., 4 tabs
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28008607.pdf
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Additional details
Publishing Information
- Imprint Title
- Principal working group 3 on primary circuit integrity
- Imprint Pagination
- 189 p.
- Journal Page Range
- p. 129-139.
- 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
- 28008607
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CRACK PROPAGATION; CRACKS; FRACTURE MECHANICS; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR SAFETY; RISK ASSESSMENT; RUPTURES; STEAM GENERATORS; STRESS CORROSION; SYSTEM FAILURE ANALYSIS
- Descriptors DEC
- BOILERS; CHEMICAL REACTIONS; CORROSION; FAILURES; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; SIMULATION; SYSTEMS ANALYSIS; THERMAL POWER PLANTS; VAPOR GENERATORS