Fluid-structure interaction (FSI) study on sodium leakage incident at prototype fast breeder reactor Monju by using ANSYS software
Creators
- 1. Institute for Nuclear Science and Technology, 179, Hoang Quoc Viet, Nghia Do, Cau Giay, Ha Noi (Viet Nam)
Description
Fluid-structure interaction (FSI) is the interaction of movable or deformable structures affected by fluid flow surrounding and plays an important role in many issues related to the industry, especially in nuclear engineering. In a nuclear power plant system, the structures working under high pressure and temperature can cause excessive force or stress to the structures resulting in mechanical damages that may eventually threaten structural integrity. This research focuses on the investigation of sodium leakage incident issues at prototype fast breeder reactor Monju by using ANSYS simulation software. By using Modal and Fluent analyses in ANSYS, a comparison between the natural frequency of thermowell and vortex shedding frequency at several operation conditions has been done, and the most dangerous case was found for FSI analysis. The results of this analysis showed a stress concentration location similar to the location of broken thermowell and the amplitude of stress large enough for fatigue damage. (author)
Additional details
Publishing Information
- ISBN
- 978 604 67 1737 9
- Imprint Title
- The VINATOM - Annual Report for 2019
- Imprint Pagination
- 282 p.
- Journal Page Range
- p. 38-45
- Report number
- VINATOM-AR--19
INIS
- Country of Publication
- Viet Nam
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 55019056
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; FLUID FLOW; FLUID-STRUCTURE INTERACTIONS; MONJU REACTOR; NUCLEAR ENGINEERING; NUCLEAR POWER PLANTS; SODIUM; VORTICES
- Descriptors DEC
- ALKALI METALS; BREEDER REACTORS; ELEMENTS; ENGINEERING; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; METALS; NUCLEAR FACILITIES; POWER PLANTS; POWER REACTORS; REACTORS; SIMULATION; SODIUM COOLED REACTORS; THERMAL POWER PLANTS
Optional Information
- Notes
- 7 refs, 9 figs, 3 tabs.
- Secondary number(s)
- VINATOM-AR--19-03