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| 1 | Mitigating check valve slamming and subsequentwater hammer events for PPFS using MOC显示文摘The method of characteristic(MOC) was adopted to analyze the check valve-induced water hammer behaviors for a Parallel Pumps Feedwater System(PPFS) during the alternate startup process.The motion of check valve disc was simulated using inertial valve model.Transient parameters including the pressure oscillation,local flow velocity and slamming of the check valve disc etc.have been obtained.The results showed that severe slamming between the valve disc and valve seat occurred during the alternate startup of parallel pumps.The induced maximum pressure vibration amplitude is up to 5.0 MPa.The scheme of appending a damping torque to slow down the check valve closing speed was also performed to mitigate of water hammer.It has been numerically approved to be an effective approach. | TIAN Wenxi SU Guanghui WANG Gaopeng QIU Suizheng XIAO Zejun | 2009 | Nuclear Science and Techniques2009，20，2： | 2 |
| 2 | Dynamic simulation of a space gas-cooled reactor power system with a closed Brayton cycle显示文摘Space nuclear reactor power(SNRP)using a gas-cooled reactor(GCR)and a closed Brayton cycle(CBC)is the ideal choice for future high-power space missions.To investigate the safety characteristics and develop the control strategies for gas-cooled SNRP,transient models for GCR,energy conversion unit,pipes,heat exchangers,pump and heat pipe radiator are established and a system analysis code is developed in this paper.Then,analyses of several operation conditions are performed using this code.In full-power steady-state operation,the core hot spot of 1293 K occurs near the upper part of the core.If 0.4$reactivity is introduced into the core,the maximum temperature that the fuel can reach is 2059 K,which is 914 K lower than the fuel melting point.The system finally has the ability to achieve a new steady-state with a higher reactor power.When the GCR is shut down in an emergency,the residual heat of the reactor can be removed through the conduction of the core and radiation heat transfer.The results indicate that the designed GCR is inherently safe owing to its negative reactivity feedback and passive decay heat removal.This paper may provide valuable references for safety design and analysis of the gas-cooled SNRP coupled with CBC. | Chenglong WANG Ran ZHANG Kailun GUO Dalin ZHANG Wenxi TIAN Suizheng QIU Guanghui SU | 2021 | Frontiers in Energy2021，15，4： | 2 |
| 3 | A fusion–fission hybrid reactor with water-cooled pressure tube blanket for energy production显示文摘 | Hongchun Wu Tiejun Zu Suizheng Qiu Xinli Gao Youqi Zheng Liangzhi Cao Wenxi Tian | 2012 | Progress in Nuclear Energy2012，，： | 1 |
| 4 | Numericalsimulation and optimization on valve-induced waterhammer characteristics for parallel pump feedwatersystem显示文摘 | TIAN Wenxi SU G H WANG Gaopeng | | Annals of Nucle0，，： | 1 |
| 5 | The Comparison of Designed Water-cooled and Air-cooled Passive Residual Heat Removal System for 300 MW Nuclear Power Plant during the Feed-water Line Break Scenario 显示文摘 | Mingiun Wang Suizheng Qiu Wenxi Tian | 2013 | Annals of Nuclear Energy2013，57，： | 1 |
| 6 | Development of a thermal-hydraulic analysis code for the pebble bed water-cooled reactor显示文摘 | CAI Xiaoyu QIU Suizheng TIAN Wenxi | 2011 | Nuclear Engineering and Design2011，241，12： | 1 |
| 7 | Development of TSACO and application to Chinese HCCB TBM cooling system显示文摘 | Jie Wang Wenxi Tian Guanghui Su Suizheng Qiu | 2013 | Fusion Engineering and Design2013，，11： | 1 |
| 8 | Numerical simulation and optimization on valve-induced water hammer characteristics for parallel pump feedwater system显示文摘 | Tian Wenxi Su G H Wang Gaopeng | 2008 | Annals of Nuclear Energy2008，35，12： | 1 |
| 9 | Numerical simulation and optimization on valve-induced water hammer characteristics for parallel pump feedwater system 显示文摘 | Tian Wenxi Su G H Wang Gaopeng | 2008 | Annals of Nuclear Energy2008，35，12： | 1 |
| 10 | Nu-merical simulation and optimization on valve-induced water hammer characteristics for parallel pump feed-water system显示文摘 | TIAN Wenxi SU G H WANG Gaopeng | 2008 | Annals of Nuclear Energy2008，35，： | 1 |
| 11 | Numerical simula-tion and optimization on valve-induced water hammer characteristics for parallel pump feedwater system 显示文摘 | Wenxi Tian Su G H Gaopeng Wang | 2008 | Annals of Nuclear Energy2008，35，12： | 1 |
| 12 | Study of traveling wave reactor (TWR) and candle strategy: A review work显示文摘 | ZHENG Meiyin TIAN Wenxi CHU Xiao | 2014 | Progress in Nuclear Energy2014，71，： | 1 |
| 13 | Numerical study on flow and heat transfer characteristics in the rod bundle channels under super critical pressure condition显示文摘 | Yang Xingbo Su G H Tian Wenxi | 2010 | Annals of Nuclear Energy2010，37，12： | 1 |
| 14 | Thermohydraulic and safety analysis on China ad- vanced research reactor under station blackout accident显示文摘 | TIAN Wenxi QIU Suizheng SU Guanghui | 2007 | Annals of Nuclear Energy2007，34，： | 1 |
| 15 | Thermohydraulic and safety analysis on China Advanced Research Reactor under station black out accident 显示文摘 | TIAN Wenxi QIU Suizheng SU Guanghui | 2007 | Annals of Nuclear Energy2007，34，4： | 1 |
| 16 | Three-dimensional study on steady thermo- hydraulics characteristics in secondary side of steam generator显示文摘 | CONG Tenglong TIAN Wenxi SU Guanghui | 2014 | Progress in Nuclear Energy2014，70，1： | 1 |
| 17 | Numerical simulation and optimization on valve-induced water hammer characteristics for parallel pump feedwater system显示文摘 | TIAN Wenxi SU G H WANG Gaopeng | 2008 | Annals of Nuclear Energy2008，3，12： | 1 |
| 18 | Development of a thermal-hydraulic safety analysis code RETAC for AP1000显示文摘 | WANG Weiwei TIAN Wenxi SU Guanghu | 2012 | Progress in Nuclear Energy2012，55，1： | 1 |
| 19 | Hepatoprotective effect of polysaccharides from Boschniakia rossica on carbon tetrachlorideinduced toxicity显示文摘 | QUAN Jishu LI Tian ZHAO Wenxi | | 0，，3： | 1 |
| 20 | Numerical Computation of Thermally Controlled Steam Bubble Condensation Using Moving Particle Semi- Implicit Method显示文摘 | Wenxi Tian Yuki Ishiwatari Satoshi Ikejiri | 2010 | Annual of Nuclear Energy2010，37，1： | 1 |
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