Zobrazeno 1 - 10
of 657
pro vyhledávání: '"Wenxi Tian"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2332-2342 (2024)
Lead-cooled fast reactors (LFRs) have a wide range of application scenarios, which require the thermal-hydraulic characteristics of LFRs to be reliable. In the present paper, the Lead-cooled fast reactor Thermal-Hydraulic Analysis Code LETHAC was dev
Externí odkaz:
https://doaj.org/article/076a9c9d45344d32976f811eea83be3c
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 2, Pp 463-471 (2024)
Average and local convective heat transfer coefficients of nitrogen are measured experimentally in an electrically heated circular tube for a range of Reynolds number from 1.08 × 104 to 3.60 × 104, and wall-to-bulk temperature ratio from 1.01 to 1.
Externí odkaz:
https://doaj.org/article/9ad165b2b2b149c1880d95a469b37955
Publikováno v:
International Journal of Advanced Nuclear Reactor Design and Technology, Vol 5, Iss 4, Pp 159-167 (2023)
External Reactor Vessel Cooling (ERVC) is a key measure to realize molten corium In-Vessel Retention (IVR). The uncertainty of severe accident in core leads to the uncertainty of molten pool parameters in lower head, which may threat the reliability
Externí odkaz:
https://doaj.org/article/a49d483f4e8a4ee5aa12fc30e4ce11b3
Autor:
Qiang Lian, Simiao Tang, Longxiang Zhu, Luteng Zhang, Wan Sun, Shanshan Bu, Liangming Pan, Wenxi Tian, Suizheng Qiu, G.H. Su, Xinghua Wu, Xiaoyu Wang
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 11, Pp 4274-4281 (2023)
Blanket is of vital importance for engineering application of the fusion reactor. Nuclear heat deposition in materials is the main heat source in blanket structure. In this paper, the three-dimensional method for thermal-hydraulics/neutronics couplin
Externí odkaz:
https://doaj.org/article/bd22565dde2641408c4423bc2615b121
Autor:
Wen Ding, Kui Zhang, Dalin Zhang, Ronghua Chen, Zhongyun Ju, Caihong Xu, Ting Wang, Wenxi Tian, Suizheng Qiu
Publikováno v:
International Journal of Advanced Nuclear Reactor Design and Technology, Vol 5, Iss 3, Pp 115-122 (2023)
The safety injection (SI) system might be put into use, and the coolant at high temperature will mix with the supcooled water under Loss Of Coolant Accident (LOCA). The thermo-hydraulic phenomena associated with the thermal mixing of coolant and supc
Externí odkaz:
https://doaj.org/article/0d995bfce24a4c298e42e5e7d705eaa4
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 8, Pp 2997-3009 (2023)
The Passive containment Air-cooling System (PAS) can effectively remove the decay heat of the modular small nuclear reactor after an accident. The details of natural convection around the dome, which is a key part of PAS, were investigated numericall
Externí odkaz:
https://doaj.org/article/bb346469984f4fe7aeecd41a89b14ac8
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 7, Pp 2534-2546 (2023)
Gas-cooled space reactor, which adopts He–Xe gas mixture as working fluid, is a better choice for megawatt power generation. In this paper, thermal-hydraulic characteristics of He–Xe gas mixture in 2 × 2 rod bundle wrapped with helical wires is
Externí odkaz:
https://doaj.org/article/57bc56cf4a9e445b88e2d9626d419092
Publikováno v:
International Journal of Advanced Nuclear Reactor Design and Technology, Vol 5, Iss 2, Pp 86-96 (2023)
In the concept of Fluoride-Salt-cooled high-Temperature Advanced Reactor (FuSTAR), the Printed Circuit Heat Exchanger (PCHE) is mainly considered in its supercritical carbon dioxide (S–CO2) Brayton cycle secondary loop. The design of the PCHE is ba
Externí odkaz:
https://doaj.org/article/615b6671c71d41aab5db8d45d47d30d0
Publikováno v:
International Journal of Advanced Nuclear Reactor Design and Technology, Vol 5, Iss 2, Pp 97-103 (2023)
Containment is the last barrier of preventing the release of radioactive fission products in a nuclear power plant (NPP). It has the top priority of its strategy in a severe accident (SA) to ensure the integrity of containment. Generally, there are t
Externí odkaz:
https://doaj.org/article/c9615ddc4f9d4fe394c97c5d0bdb0937
Publikováno v:
International Journal of Advanced Nuclear Reactor Design and Technology, Vol 5, Iss 1, Pp 1-8 (2023)
The nanoscale liquid sodium film inside the microporous wick structure is of great importance to understanding the evaporation mechanism of the sodium heat pipe. The novel optimized wick structure is made of several layers of special screen. The surf
Externí odkaz:
https://doaj.org/article/9adecf25d740475883d13f8f483137d5