Published 2004 | Version v1
Miscellaneous

Failure probability estimation for axial through-wall cracked steam generator tubes

  • 1. Sungkyunkwan University, Seoul (Korea, Republic of)
  • 2. Korea Atomic Energy Research Institute, Taejon (Korea, Republic of)

Description

Steam generator tubes in pressurized water reactor (PWR) are exposed to various types of degradation and aging processes which might significantly decrease its structural reliability. Up to now, integrity evaluations are performed by using conventional deterministic approaches. However, there are lots of uncertainties to perform a rational evaluation of lifetime. In this respect, a probabilistic safety assessment method is more appropriate for the assessment of overall steam generator tube safety. The objective of this study is to estimate the failure probability of steam generator tubes containing a single through-wall cracks. Major input variables such as crack length, yield strength and ultimate tensile strength are considered as probabilistic variables. A limit load solution is used to constitute a limit state function. In the analyses, failure probabilities are calculated by using the FORM (First Order Reliability Method), SORM (Second Order Reliability Method), and MC (Monte Carlo) simulation method

Part of:
Proceedings of the KNS autumn meeting

Additional details

Publishing Information

Publisher
KNS
Imprint Place
Taejon (Korea, Republic of)
Imprint Title
Proceedings of the KNS autumn meeting
Imprint Pagination
1466 p.
Journal Page Range
p. 339-340

Conference

Title
2004 autumn meeting of the KNS
Dates
28-29 Oct 2004
Place
Yongpyong (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
36102327
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
COMPUTERIZED SIMULATION; EVALUATION; FAILURES; PROBABILISTIC ESTIMATION; PWR TYPE REACTORS; RELIABILITY; STEAM GENERATORS; TUBES
Descriptors DEC
BOILERS; CALCULATION METHODS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
5 refs, 1 fig, 1 tab