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 (3.0 MB)

Name Size Download all
md5:cba25a366149710df8bc7d957b362efa
3.0 MB Preview Download

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