Integrity assessment of steam generator tubes based on elastic-plastic fracture mechanics concept
- 1. School of Mechanical Engineering, Sungkyunkwan Univ., Gyeonggi (Korea, Republic of)
- 2. Korea Atomic Energy Research Inst., Daejeon (KR)
Description
Operating experience of steam generators in nuclear power plants shows that constituent tubes are affected by diverse degradation mechanisms. The cracked tube can stay in service if sufficient structural margin is assured to preclude the risk of failure. With regard to estimation of the maximum load carrying capacity, most of preceding researches were focused on limit load concept but extensive test data would be needed to endow confidence of the relevant solution. In contrast to this, up to now, integrity assessment scheme based on the elastic-plastic fracture mechanics concept has not been settled despite of its efficiency. In this paper, elastic-plastic finite element analyses of cracked steam generator tubes are carried out. Fracture toughness of the typical tube material is also measured and the crack instability is evaluated by comparing the crack driving force with fracture toughness of the tube material. Analysis results show that the elastic-plastic fracture mechanics method predicts the load carrying capacities accurately compared to the experimental data. Thus, it is anticipated that the elastic-plastic fracture mechanics concept can be applied to integrity assessment of steam generator tubes with through-wall cracks. (author)
Availability note (English)
Available from Japan Society of Mechanical Engineers, 35 Shinanomachi, Shinjuku-ku, Tokyo 160-0016, JapanAdditional details
Publishing Information
- Publisher
- Japan Society of Mechanical Engineers
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the ICONE-15 (Revised). The 15th international conference on nuclear engineering
- Imprint Pagination
- [3174 p.]
- Journal Page Range
- [6 p.]
Conference
- Title
- 15. international conference on nuclear engineering
- Acronym
- ICONE-15
- Dates
- 22-26 Apr 2007
- Place
- Nagoya, Aichi (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 39048702
- Subject category
- S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; CRACKS; ELASTICITY; FAILURES; FINITE ELEMENT METHOD; FRACTURE MECHANICS; FRACTURE PROPERTIES; INCONEL 600; NUMERICAL ANALYSIS; PLASTICITY; PWR TYPE REACTORS; STEAM GENERATORS; TUBES
- Descriptors DEC
- ALLOY-NI76CR15FE8; ALLOYS; ALUMINIUM ADDITIONS; ALUMINIUM ALLOYS; BOILERS; CALCULATION METHODS; CHROMIUM ALLOYS; COMPUTER CODES; CORROSION RESISTANT ALLOYS; ENRICHED URANIUM REACTORS; HEAT RESISTANT MATERIALS; HEAT RESISTING ALLOYS; INCONEL ALLOYS; IRON ALLOYS; MATERIALS; MATHEMATICAL SOLUTIONS; MATHEMATICS; MECHANICAL PROPERTIES; MECHANICS; NICKEL ALLOYS; NICKEL BASE ALLOYS; NIMONIC; NUMERICAL SOLUTION; POWER REACTORS; REACTORS; THERMAL REACTORS; TITANIUM ADDITIONS; TITANIUM ALLOYS; TRANSITION ELEMENT ALLOYS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- This CD-ROM can be used for WINDOWS 9x/NT/2000/ME/XP, MACINTOSH; Acrobat Reader is included; Data in PDF format, Folder Name Final Paper, Paper ID ICONE15-10428.pdf; 14 refs., 7 figs., 3 tabs.