Results 1 to 10 of about 1,546,971 (249)

Applicability research of round tube CHF mechanistic model in rod bundle channel

Nuclear Engineering and Technology, 2021
In view of the complex geometric structure of the rod bundle channel and the limitation of the current CHF visualization experiment technology, it is very difficult to obtain the rod bundle CHF mechanism directly through the phenomenon of the rod bundle ...
Wei Liu, Shinian Peng, Jianqiang Shan, Guangming Jiang, Yu Liu, Jian Deng, Ying Hu   +6 more
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Improvement of crossflow model of MULTID component in MARS-KS with inter-channel mixing model for enhancing analysis performance in rod bundle

Nuclear Engineering and Technology, 2023
MARS-KS, a domestic regulatory confirmatory code of Republic of Korea, had been developed by integrating RELAP5/MOD2 and COBRA-TF. The integration of COBRA-TF allowed to extend the capability of MARS-KS, limited to one-dimensional analysis, to multi ...
Yunseok Lee, Taewan Kim
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An experimental investigation of void fraction characteristics of flow boiling in a 5×5 rod bundle channel

Case Studies in Thermal Engineering
Flow boiling in the rod bundle channel is an important phenomenon in nuclear reactors. The local inhomogeneous void fraction distribution in the flow channel will affect the flow and heat transfer in two phase flow.
Sui-Jun Gong, Jing-Liang Bi, Yan-Ping Huang, Wen-Xiong Zhou, De-Wen Yuan, Jian-Jun Xu   +5 more
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Numerical Simulation and Experimental Study on Gas Flow in an Open Lattice Structure for an Advanced Space Nuclear Power System

Frontiers in Energy Research, 2022
Helium flow in the rod bundle channel with an open lattice structure is an important phenomenon for the advanced gas-cooled nuclear core design. In this study, thermal analysis with helium flow in various channel designs is conducted based on CFD methods
Zhipeng Wang, Zhipeng Wang, Zhipeng Wang, Jing Zhao, Jing Zhao, Jing Zhao, Zishen Ye, Zishen Ye, Zishen Ye, Lei Shi, Lei Shi, Lei Shi   +11 more
doaj   +1 more source

Investigation on Rod Bundle CHF Mechanistic Model for DNB and DO Prediction Under Wide Parameter Range

Frontiers in Energy Research, 2021
For a water cooled reactor, the key thermal-hydraulic parameters span a wide range corresponding to different CHF regimes. Under accident conditions, due to the flow regime transition and interchannel mixing effect, the corresponding CHF can transition ...
Wei Liu, Shinian Peng, Guangming Jiang, Yu Liu   +3 more
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Numerical Study on Rising Behavior of Single Bubble in Petal-shaped Rod Bundle Channel

Yuanzineng kexue jishu, 2023
Bubble behavior has a significant impact on the characteristics of two-phase flow and heat transfer. To investigate the dynamics of bubbles in a petal-shaped rod bundle channel, the behavior of bubbles in static water in the rod bundle channel was ...
ZHANG Wenchao1,2;LI Jiayuan1;YANG Guang1;SUN Jianchuang1;JIN Guangyuan1;CAI Weihua1
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The effects of spacer grid arrangement on flow boiling characteristics and critical heat flux in a complex 5 × 5 rod bundle channel

Case Studies in Thermal Engineering, 2022
In this study, a numerical model of two-phase flow boiling in a rod bundle channel was developed to investigate the influence of spacer grid's arrangement on thermal-hydraulic characteristics and critical heat flux (CHF).
Xusheng Wang, Yingwen Liu
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Experimental Study on the Transition Characteristics and Criterion From Wall-Peak to Core-Peak Phase Distribution in Vertical Rod Bundles

Frontiers in Energy Research, 2021
Aiming at understanding the phase distribution characteristics and developing the transition criterion from wall-peak to core-peak phase distribution in a rod bundle channel, air–water two-phase flow experiments were conducted in 5 × 5 rod bundles in the
Quan-yao Ren, Zengping Pu, Ping Chen, Liang-ming Pan, Fawen Zhu, Meiyin Zheng, Haoyu Wang, Lie Wei, Hui He   +8 more
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Void fraction distribution in a rod bundle with part-length rods via high-energy X-ray computed tomography

Mechanical Engineering Journal, 2021
The void fraction distribution of a fuel rod bundle in a boiling water reactor is a critical parameter for accurately predicting the optimal thermal margin in the design of a reactor core. The rod bundle configuration, such as a part-length rod (PLR) and
Takahiro ARAI, Atsushi UI, Masahiro FURUYA, Riichiro OKAWA, Tsugumasa IIYAMA, Shota UEDA, Kenetsu SHIRAKAWA, Kazuaki KITO   +7 more
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Large eddy simulation on the turbulent mixing phenomena in 3×3 bare tight lattice rod bundle using spectral element method

Nuclear Engineering and Technology, 2020
Subchannel code is one of the effective simulation tools for thermal-hydraulic analysis in nuclear reactor core. In order to reduce the computational cost and improve the calculation efficiency, empirical correlation of turbulent mixing coefficient is ...
Haoran Ju, Mingjun Wang, Yingjie Wang, Minfu Zhao, Wenxi Tian, Tiancai Liu, G.H. Su, Suizheng Qiu   +7 more
doaj   +1 more source