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RISS 인기검색어
- 검색키워드
- 저자 : Duan Chengjie (검색결과 4 건)
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The optimization for the straight-channel PCHE size for supercritical CO<sub>2</sub> Brayton cycle
Xu, Hong,Duan, Chengjie,Ding, Hao,Li, Wenhuai,Zhang, Yaoli,Hong, Gang,Gong, Houjun Korean Nuclear Society 2021 Nuclear Engineering and Technology Vol.53 No.6
Printed Circuit Heat Exchanger (PCHE) is a widely used heat exchanger in the supercritical carbon dioxide (sCO<sub>2</sub>) Brayton cycle because it can work under high temperature and pressure, and has been a hot topic in Next Generation Nuclear Plant (NGNP) projects for use as recuperators and condensers. Most previous studies focused on channel structures or shapes. However, no clear advancement has so far been seen in the allover size of the PCHE. In this paper, we proposed an optimal size of the PCHE with a fixed volume. Two boundary conditions of PCHE were simulated, respectively. When the volume of PCHE was fixed, the heat transfer rate and pressure loss were picked as the optimization objectives. The Pareto front was obtained by the Multi-objective optimization procedure. We got the optimized number of PCHE channels under two different boundary conditions from the Pareto front. The comprehensive performance can be increased by 5.3% while holding in the same volume. The numerical results from this study can be used to improve the design of PCHE with straight channels.
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Preliminary conceptual design of a small high-flux multi-purpose LBE cooled fast reactor
Xiong Yangbin,Duan Chengjie,Zeng Qin,Ding Peng,Song Juqing,Zhou Junjie,Xu Jinggang,Yang Jingchen,Li Zhifeng 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.8
The design concept of a Small High-flux Multipurpose LBE(Lead Bismuth Eutectic) cooled Fast Reactor (SHMLFR) was proposed in the paper. The primary cooling system of the reactor is forced circulation, and the fuel element form is arc-plate loaded high enrichment MOX fuel. The core is cylindrical with a flux trap set in the center of the core, which can be used as an irradiation channel. According to the requirements of the core physical design, a series of physical design criteria and constraints were given, and the steady and transient parameters of the reactor were calculated and analyzed. Regarding the thermal and hydraulic phenomena of the reactor, a simplified model was used to conduct a preliminary analysis of the fuel plates at special positions, and the temperature field distribution of the fuel plate with the highest power density under different coolant flow rates was simulated. The results show that the various parameters of SHMLFR meet the requirements and design criteria of the physical design of the core and the thermal design of the reactor. This implies that the conceptual design of SHMLFR is feasible
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Pengfei Wang,Peng Ding,Wenhuai Li,Rongshun Xie,Chengjie Duan,Gang Hong,Yaoli Zhang 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.3
An experimental study has been conducted to investigate the heat transfer characteristics of supercriticalcarbon dioxide (sCO2) uniformly heated in the horizontal circular smooth tube. The results illustratedthat there was a significant difference in heat transfer between the top wall and bottom wall due to thebuoyancy. Bulk flow acceleration cannot be negligible in the high heat flux region, which leads to heattransfer deterioration. A new heat transfer correlation is proposed, in which the buoyancy parameter andbulk flow acceleration have been taken into account. The new correlation and six classic correlations forsCO2 are examined in horizontal tubes. The comparison indicates that the new correlation has a betterperformance for sCO2 flowing through a horizontal heating tube under natural circulation conditions. Forexample, 94.9% of the calculated results using the new heat transfer correlation were within ±30% of theexperimental results while only 87.9% of that using the Jackson correlation (the best of the six) werewithin the same error bands.
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Artificial neural network reconstructs core power distribution
Wenhuai Li,Peng Ding,Wenqing Xia,Shu Chen,Fengwan Yu,Chengjie Duan,Dawei Cui,Chen Chen 한국원자력학회 2022 Nuclear Engineering and Technology Vol.54 No.2
To effectively monitor the variety of distributions of neutron flux, fuel power or temperatures in thereactor core, usually the ex-core and in-core neutron detectors are employed. The thermocouples fortemperature measurement are installed in the coolant inlet or outlet of the respective fuel assemblies. Itis necessary to reconstruct the measurement information of the whole reactor position. However, thereading of different types of detector in the core reflects different aspects of the 3D power distribution. The feasibility of reconstruction the core three-dimension power distribution by using different combinations of in-core, ex-core and thermocouples detectors is analyzed in this paper to synthesize theuseful information of various detectors. A comparison of multilayer perceptron (MLP) network and radialbasis function (RBF) network is performed. RBF results are more extreme precision but also moresensitivity to detector failure and uncertainty, compare to MLP networks. This is because that localizedneural network could offer conservative regression in RBF. Adding random disturbance in trainingdataset is helpful to reduce the influence of detector failure and uncertainty. Some convolution neuralnetworks seem to be helpful to get more accurate results by use more spatial layout information, thoughrelative researches are still under way
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