Zobrazeno 1 - 10
of 25
pro vyhledávání: '"Liancheng Guo"'
Autor:
Md Abdur Rob Sheikh, Xiaoxing Liu, Tatsuya Matsumoto, Koji Morita, Liancheng Guo, Tohru Suzuki, Kenji Kamiyama
Publikováno v:
Energies, Vol 13, Iss 19, p 5018 (2020)
In the safety analysis of sodium-cooled fast reactors, numerical simulations of various thermal-hydraulic phenomena with multicomponent and multiphase flows in core disruptive accidents (CDAs) are regarded as particularly difficult. In the material r
Externí odkaz:
https://doaj.org/article/c00a14cee6e14f90b1813596920ae36c
Publikováno v:
Mechanical Engineering Journal, Vol 1, Iss 4, Pp TEP0024-TEP0024 (2014)
The postulated core disruptive accidents (CDAs) are regarded as particular difficulties in the safety analysis of liquid-metal fast reactors (LMFRs). In the CDAs, the self-leveling behavior of debris bed is a crucial issue, which greatly affects the
Externí odkaz:
https://doaj.org/article/26afd946f2214a458a5d3e1c4602f249
Publikováno v:
Nuclear Engineering and Design. 315:61-68
The postulated core disruptive accidents (CDAs) are regarded as particular difficulties in the safety analysis of liquid-metal fast reactors (LMFRs). In the CDAs, core debris may settle on the core-support structure and form conic bed mounds. Then de
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::829e9627b19f469de5c7eb5c821186ac
https://doi.org/10.1016/j.nucengdes.2017.02.024
https://doi.org/10.1016/j.nucengdes.2017.02.024
Publikováno v:
Nuclear Technology. 196:588-597
The lumped heat transfer methodology is simple, and the solution is very fast, so the lumped parameter approach has been widely used in thermal-hydraulic analysis for fuel pin heat transfer in nucl...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::68f9cddb5f2b6b131e2c87288037a23a
https://doi.org/10.13182/nt16-5
https://doi.org/10.13182/nt16-5
Publikováno v:
International Journal of Hydrogen Energy. 41:7227-7232
Fuel-coolant interaction (FCI) is a very complex but important issue in the safety analysis of the severe accidents for nuclear reactors due to the rapid multiple thermos–hydrodynamic activities. Until now, there are still large uncertainties exist
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::167366707fa67e399345e1ba089c40b4
https://doi.org/10.1016/j.ijhydene.2016.01.080
https://doi.org/10.1016/j.ijhydene.2016.01.080
Autor:
Kenji Kamiyama, Yoshiharu Tobita, Ken Ichi Matsuba, Tohru Suzuki, Hirotaka Tagami, Hidemasa Yamano, Liancheng Guo, Koji Morita, Bin Zhang, Mikio Isozaki
Publikováno v:
Journal of Nuclear Science and Technology. 53:698-706
The in-vessel retention (IVR) of core disruptive accident (CDA) is of prime importance in enhancing safety characteristics of sodium-cooled fast reactors (SFRs). In the CDA of SFRs, molten core material relocates to the lower plenum of reactor vessel
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::689a0dc4ab62ab8d2f532694ce1b7732
https://doi.org/10.1080/00223131.2016.1143409
https://doi.org/10.1080/00223131.2016.1143409
Publikováno v:
International Journal for Numerical Methods in Fluids. 82:334-347
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d4d1a8f36a76fc08c52430c0d906ea56
https://doi.org/10.1002/fld.4220
https://doi.org/10.1002/fld.4220
Autor:
Xiaoxing Liu, Tatsuya Matsumoto, Abdur Rob Sheikh, Koji Morita, Kenji Kamiyama, Liancheng Guo, Tohru Suzuki
Publikováno v:
Energies, Vol 13, Iss 5018, p 5018 (2020)
Energies, 13 (19), Art.-Nr. 5018
Energies; Volume 13; Issue 19; Pages: 5018
Energies, 13 (19), Art.-Nr. 5018
Energies; Volume 13; Issue 19; Pages: 5018
In the safety analysis of sodium-cooled fast reactors, numerical simulations of various thermal-hydraulic phenomena with multicomponent and multiphase flows in core disruptive accidents (CDAs) are regarded as particularly difficult. In the material r
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::40443a012a3eb62b551a2cf568f825ba
https://doi.org/10.3390/en13195018
https://doi.org/10.3390/en13195018
Publikováno v:
Journal of Nuclear Science and Technology. 53:271-280
For the analysis of debris behavior in core disruptive accidents of liquid metal fast reactors, a hybrid computational tool was developed using the discrete element method (DEM) for calculation of solid particle dynamics and a multi-fluid model of a
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::34f714a68183c3f5cac363de6840c2b7
https://doi.org/10.1080/00223131.2015.1043156
https://doi.org/10.1080/00223131.2015.1043156
Publikováno v:
Journal of Nuclear Science and Technology. 52:1480-1489
We want to simulate, based on particle methods, the dynamic behavior of multi-phase flows in a gas–solid–liquid mixture system. With the governing equations discretized within the finite volume particle method, the effects of contact and collisio
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3d809f7182e3feda3822a1361df01571
https://doi.org/10.1080/00223131.2015.1012132
https://doi.org/10.1080/00223131.2015.1012132