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Simulation study of steam flow behavior and piping mechanical response analysis in safety valve discharge pipes with fluid-structure interaction

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Názov: Simulation study of steam flow behavior and piping mechanical response analysis in safety valve discharge pipes with fluid-structure interaction
Autori: Shasha Yin, Xietian Ji, Xiaodong Lu, Qi Zhang
Zdroj: International Journal of Advanced Nuclear Reactor Design and Technology, Vol 7, Iss 3, Pp 308-318 (2025)
Informácie o vydavateľovi: Elsevier BV, 2025.
Rok vydania: 2025
Predmety: Fluid-structure interaction, TK9001-9401, Piping stress, Nuclear engineering. Atomic power, Transonic-supersonic flow regimes, Safety valve discharge pipe
Popis: This study numerically simulates the steam flow behavior and piping mechanical response within the safety valve discharge piping of a nuclear power system. A one-way Fluid-Structure Interaction (FSI) approach was employed to simulate high-temperature saturated steam flow through an adiabatic pipe featuring three 90° right-angle bends. Model reliability was ensured via mesh independence verification and comparison with theoretical solutions. Analysis of steam flow parameter distribution and pipe stress-strain characteristics under mass flow inlet and pressure inlet boundary conditions reveals that centrifugal forces and Dean vortices induce significant pressure/velocity stratification within the elbow region. A low-pressure stagnation zone along the inner wall coexists with a high-velocity zone on the outer wall, amplifying localized energy dissipation. Under low-pressure conditions (0.8 MPa), steam compressibility triggers flow transition, generating supersonic flow (Ma = 1.77) at the outer elbow. Boundary conditions critically govern mechanical responses, with pressure inlet conditions causing abrupt fluid kinetic energy surges that elevate elbow impact stress to 430.39 MPa-surpassing the material yield limit. The second elbow emerges as a structural vulnerability due to cumulative upstream vortices, exhibiting maximum strain of 12.09 mm.
Druh dokumentu: Article
Jazyk: English
ISSN: 2468-6050
DOI: 10.1016/j.jandt.2025.07.006
Prístupová URL adresa: https://doaj.org/article/d39d790975074c1dace38649f57d0ef3
Rights: CC BY NC ND
Prístupové číslo: edsair.doi.dedup.....97bcaa8df7515ffff21221d85ac35b80
Databáza: OpenAIRE
Popis
Abstrakt:This study numerically simulates the steam flow behavior and piping mechanical response within the safety valve discharge piping of a nuclear power system. A one-way Fluid-Structure Interaction (FSI) approach was employed to simulate high-temperature saturated steam flow through an adiabatic pipe featuring three 90° right-angle bends. Model reliability was ensured via mesh independence verification and comparison with theoretical solutions. Analysis of steam flow parameter distribution and pipe stress-strain characteristics under mass flow inlet and pressure inlet boundary conditions reveals that centrifugal forces and Dean vortices induce significant pressure/velocity stratification within the elbow region. A low-pressure stagnation zone along the inner wall coexists with a high-velocity zone on the outer wall, amplifying localized energy dissipation. Under low-pressure conditions (0.8 MPa), steam compressibility triggers flow transition, generating supersonic flow (Ma = 1.77) at the outer elbow. Boundary conditions critically govern mechanical responses, with pressure inlet conditions causing abrupt fluid kinetic energy surges that elevate elbow impact stress to 430.39 MPa-surpassing the material yield limit. The second elbow emerges as a structural vulnerability due to cumulative upstream vortices, exhibiting maximum strain of 12.09 mm.
ISSN:24686050
DOI:10.1016/j.jandt.2025.07.006