Steam generator tube rupture simulation using extended finite element method
Description
Highlights: • Extended finite element method used for modeling the steam generator tube rupture. • Crack propagation is modeled in an arbitrary solution dependent path. • The FE model is used for estimating the rupture pressure of steam generator tubes. • Crack coalescence modeling is also demonstrated. • The method can be used for crack modeling of tubes under severe accident condition. - Abstract: A steam generator (SG) is an important component of any pressurized water reactor. Steam generator tubes represent a primary pressure boundary whose integrity is vital to the safe operation of the reactor. SG tubes may rupture due to propagation of a crack created by mechanisms such as stress corrosion cracking, fatigue, etc. It is thus important to estimate the rupture pressures of cracked tubes for structural integrity evaluation of SGs. The objective of the present paper is to demonstrate the use of extended finite element method capability of commercially available ABAQUS software, to model SG tubes with preexisting flaws and to estimate their rupture pressures. For the purpose, elastic–plastic finite element models were developed for different SG tubes made from Alloy 600 material. The simulation results were compared with experimental results available from the steam generator tube integrity program (SGTIP) sponsored by the United States Nuclear Regulatory Commission (NRC) and conducted at Argonne National Laboratory (ANL). A reasonable correlation was found between extended finite element model results and experimental results.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.nucengdes.2016.06.031Additional details
Identifiers
- DOI
- 10.1016/j.nucengdes.2016.06.031;
- PII
- S0029-5493(16)30192-3;
Publishing Information
- Journal Title
- Nuclear Engineering and Design
- Journal Volume
- 305
- Journal Page Range
- p. 697-705
- ISSN
- 0029-5493
- CODEN
- NEDEAU
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 48060475
- Subject category
- S42: ENGINEERING; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- ANL; COMPUTER CODES; CRACK PROPAGATION; CRACKS; FATIGUE; FINITE ELEMENT METHOD; INCONEL 600; PWR TYPE REACTORS; RUPTURES; SEVERE ACCIDENTS; STEAM GENERATORS; STRESS CORROSION; TUBES; US NRC
- Descriptors DEC
- ACCIDENTS; ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; BEYOND-DESIGN-BASIS ACCIDENTS; BOILERS; CALCULATION METHODS; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; FAILURES; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; MATHEMATICAL SOLUTIONS; MECHANICAL PROPERTIES; NATIONAL ORGANIZATIONS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; US AEC; US DOE; US ERDA; US ORGANIZATIONS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.