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