Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Jiesheng Min"'
Publikováno v:
Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle.
The primary loop in nuclear power plants (NPPs) consists of piping and pressure vessel, which operate under a high level of pressure and temperature. During the long-term service, these sections need to have their integrity analyzed to check whether
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1c15027455804031c34e86df6988ad65
https://doi.org/10.1115/icone29-93082
https://doi.org/10.1115/icone29-93082
Publikováno v:
Volume 8: Computational Fluid Dynamics (CFD) and Applications.
Computation-expensive problems have become more common in nuclear industry, originating from expensive analysis with the aim of reaching high accuracy. To overcome this challenge, surrogate modelling techniques are often proposed. Passive containment
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6d7c6004cff2c30d505fe16d723e9019
https://doi.org/10.1115/icone29-92164
https://doi.org/10.1115/icone29-92164
Publikováno v:
Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology.
Numerical simulation is a key technology for improvement of nuclear reactor design and maintenance with its low cost and safety comparing to traditional experiments, especially when irradiation is involved. Various software exist today in the fields
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::68cecf9a7d6aec41168cc32b5bacacf8
https://doi.org/10.1115/icone29-93008
https://doi.org/10.1115/icone29-93008
Publikováno v:
Nuclear Engineering and Design. 348:24-36
One of the major difficulties in modelling the steam condensation in the containment under accidental scenarios arises from the complicated flow patterns. Although empirical correlations have been established to predict the heat and the mass transfer
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e9290b6b896464da2b55fad86d7a8578
https://doi.org/10.1016/j.nucengdes.2019.04.012
https://doi.org/10.1016/j.nucengdes.2019.04.012
Publikováno v:
Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues.
The flow rate distribution at the entrance of the core plays a key role for reactor design since it has important implications for the performance, and efficient safety of a nuclear reactor. When the coolant passes from the downcomer to the core, it
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ccb9d379fe3bc66279b03675f2689f97
https://doi.org/10.1115/icone25-67767
https://doi.org/10.1115/icone25-67767
Publikováno v:
Volume 6: Thermal-Hydraulics.
Flow characteristic in upper plenum has a strong influence on reactor functional margin and rod cluster control assembly (RCCA) guide tube wear. Upper plenum flow governs loops flow rate measurement via hot leg temperature which has also an influence
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::5057a3b7a41e669aee83ae5623dd8cfe
https://doi.org/10.1115/icone25-68008
https://doi.org/10.1115/icone25-68008
Publikováno v:
Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues.
During accidental situations, large quantities of hydrogen are generated and released due to metal-water reaction. Eventual stratification formed in the top region of containment and locally high concentration threatens the integrity of nuclear power
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::781ab7496a7b964c4321c7da5005a573
https://doi.org/10.1115/icone25-67027
https://doi.org/10.1115/icone25-67027
Publikováno v:
The Proceedings of the International Conference on Nuclear Engineering (ICONE). :2130
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::21625a6eb0f9f250097a5ac7a092b991
https://doi.org/10.1299/jsmeicone.2019.27.2130
https://doi.org/10.1299/jsmeicone.2019.27.2130
Publikováno v:
Volume 3: Thermal-Hydraulics.
The coolant flow in the reactor pressure vessel (RPV) lower plenum is complex due to the presence of various internal structures, which has a great influence on the flow distribution at the core inlet. In order to study the thermal hydraulic characte
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3752ab7fd912ea81b4f2396dea7ac976
https://doi.org/10.1115/icone24-61013
https://doi.org/10.1115/icone24-61013
Autor:
Hongsheng Guo, M. Talbaut, Jiesheng Min, Françoise Baillot, Eric Domingues, Béatrice Patte-Rouland
Publikováno v:
Proceedings of the Combustion Institute. 33:1071-1078
Air-side dilution on laminar methane/air diffusion flames in the buoyant regime was extensively studied. CO₂, important for EGR and fire safety, was chosen as a diluent. It was complemented by N₂ and Ar. Flame stability, its external aspect and i
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::44231acdc97654858d59cc4f25eda265
https://doi.org/10.1016/j.proci.2010.06.100
https://doi.org/10.1016/j.proci.2010.06.100