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