Zobrazeno 1 - 10
of 506
pro vyhledávání: '"System code"'
Autor:
Xiaoyu Wang, Zhifang Qiu, Shinian Peng, Jian Deng, Wei Zeng, Luguo Liu, Xilin Zhang, Xue Zhang, Yunfeng Xia, Mingjun Wang
Publikováno v:
Frontiers in Energy Research, Vol 12 (2024)
Reactor thermal-hydraulic codes can be categorized into system codes, sub-channel codes and CFD (computational fluid dynamics) codes according to the spatial discretization and simplification methods. As a traditional reactor system safety analysis c
Externí odkaz:
https://doaj.org/article/6ca8003fc0014e78831a4e7497e0c843
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 1, Pp 19-33 (2024)
In nuclear thermal-hydraulic system codes, most correlations used for vertical pipes, under downward two-phase flow, have been developed considering small pipes or pool systems. This suggests that there could be uncertainties in applying the correlat
Externí odkaz:
https://doaj.org/article/09bdd20d95434013ac19ca4e79819691
Autor:
Marcos S. Sena, Yassin A. Hassan
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 9, Pp 3320-3325 (2023)
The scaled water-cooled Reactor Cavity Cooling System (RCCS) experimental facility reproduces a passive safety feature to be implemented in Generation IV nuclear reactors. It keeps the reactor cavity and other internal structures in operational condi
Externí odkaz:
https://doaj.org/article/842a4c0c4c45439cbcd46c027496f105
Publikováno v:
Yuanzineng kexue jishu, Vol 56, Iss 11, Pp 2262-2271 (2022)
High temperature gas reactors (HTGRs) have broad application prospects in power supply, seawater desalination and hydrogen production. Helical coil steam generators have the advantages of compact structure, high heat transfer efficiency and resistanc
Externí odkaz:
https://doaj.org/article/5bae8bc864c142aabde0b879207409d7
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 10, Pp 3962-3973 (2022)
Several critical heat flux (CHF) correlations including the look-up table in the MARS code have been assessed for the prediction of CHF in a downward-flow narrow rectangular channel. For the assessment, we built an experiment database that covers pre
Externí odkaz:
https://doaj.org/article/5f46aa058cfa4ec6b61fdb38bd8308c7
Publikováno v:
Yuanzineng kexue jishu, Vol 56, Iss 6, Pp 989-1004 (2022)
Safe and reliable energy supply is the key foundation for the development of unmanned underwater vehicle (UUV). Unlike land and space missions, underwater missions are more demanding on energy, which requires higher power level, longer operating time
Externí odkaz:
https://doaj.org/article/e3bf4710e7884f3b8aa88facca5c544c
Autor:
Takashi Hibiki, Jae Jun Jeong
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 4, Pp 1495-1507 (2022)
The improvement of thermal-hydraulic analysis techniques is essential to ensure the safety and reliability of nuclear power plants. The one-dimensional two-fluid model has been adopted in state-of-the-art thermal-hydraulic system codes. Current const
Externí odkaz:
https://doaj.org/article/4ac40748f6284f90bc4dbfdd57c68dae
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 11, Pp 3580-3596 (2021)
An integral test facility, PILLAR, was commissioned, aiming to provide valuable experimental results which can be referenced by system and component designers and used for the performance demonstration of liquid-metal-cooled, passive small modular re
Externí odkaz:
https://doaj.org/article/8cd36f0c38a8437395faa913ce9aacdf
Publikováno v:
Frontiers in Energy Research, Vol 10 (2022)
A steady state model of the NuScale reactor has been built using the thermal hydraulic module CESAR of the severe accident code ASTEC. Construction of the model was achieved through iterations based on convergence towards data provided by NuScale per
Externí odkaz:
https://doaj.org/article/219a94e03840473fadefb66f8067fa9e
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 9, Pp 2775-2787 (2021)
At present, most of the widely used system codes for nuclear safety analysis are one-dimensional, which cannot effectively simulate the flow field of the reactor core or other structures. This is true even for the system codes containing three-dimens
Externí odkaz:
https://doaj.org/article/05c6057b5a74490aa5b256ff79a8fb16