Published 1996 | Version v1
Report

Development of Analysis Procedure for Russian.NPP Piping Failure Probability on the Basis of R6 Crack Resistance Assessment Method

  • 1. ECS MAE RDIPE (Russian Federation)

Description

Current failure criteria (M-01-88, M-02-91, etc.) used in Russian nuclear institutions had been developed for deterministic analyses and therefore an attempt to use them for probabilistic ones has demonstrated some deficiencies inherent to them. They can include a polygonal failure surface in the space of random variables that makes this surface un-differentiable at some point. Moreover, the failure criteria are assumed by such mathematical expressions which sometimes loses their meaning in the area of lower tail values in random distributions. In this connection, this work has considered as a criterion basis the R6 criterion which sufficiently avoids the aforementioned deficiencies and has illustrated experimentally the conservatism of its assessment. A detailed analysis has been carried out to evaluate a failure probability of a perlite weld in the primary circuit piping of Russian NPPs. The experience gained in carrying out these calculations allows the assertion that the algorithm CL of FPI methods can be applied successfully to evaluate a structure failure probability using the R6 methods (This paper is a 3 page abstract)

Part of:
Proceedings of a NEA workshop on probabilistic structure integrity analysis and its relationship to deterministic analysis

Additional details

Publishing Information

Imprint Title
Proceedings of a NEA workshop on probabilistic structure integrity analysis and its relationship to deterministic analysis
Imprint Pagination
276 p.
Journal Page Range
p. 226-228
Report number
NEA-CSNI-R--1996-4

Conference

Title
NEA workshop on probabilistic structure integrity analysis and its relationship to deterministic analysis
Dates
28 Feb - 1 Mar 1996
Place
Stockholm (Sweden)

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
43012340
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS; S42: ENGINEERING;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CRACK PROPAGATION; DETERMINISTIC ESTIMATION; FAILURES; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; REACTOR COMPONENTS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; RUSSIAN FEDERATION; SAFETY ENGINEERING; SYSTEM FAILURE ANALYSIS
Descriptors DEC
CALCULATION METHODS; EASTERN EUROPE; ENGINEERING; EUROPE; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; SYSTEMS ANALYSIS; THERMAL POWER PLANTS

Optional Information

Secondary number(s)
OCDE-GD--96-124