当前位置: X-MOL首页全球导师 国内导师 › 张亚培

个人简介

张亚培,男,1984年6月生,工学博士,西安交通大学副教授。2013年6月获西安交通大学核科学与技术学科博士学位。2011.9-2012.8赴德国卡尔斯鲁厄研究所交流学习,在欧盟严重事故研究项目负责及协调人ALEXI博士带领下开展严重事故条件下堆芯熔融池换热特性机理研究,参与了德国KIT三维LIVE实验研究及数值分析工作。

研究领域

主要研究方向为先进核反应堆严重事故机理及现象学、热工水力与安全分析、钠冷快堆热工水力等。

近期论文

查看导师最新文章 (温馨提示:请注意重名现象,建议点开原文通过作者单位确认)

Zhang Yapei, Qiu Suizheng, Su Guanghui, Tian Wenxi. Analysis of safety margin of in-vessel retention for AP1000[J]. Nuclear Engineering and Design, 2010, 240: 2023-2033. Zhang Yapei, Qiu Suizheng, Su Guanghui, Tian Wenxi. Analytical model for CHF in narrow gaps with surface orientation effects[J]. Annals of Nuclear Energy, 2011, 38: 989–994. Zhang Yapei, Qiu Suizheng, Su Guanghui, Tian Wenxi. A simple novel analysis procedure for IVR calculation in core-molten severe accident[J]. Nuclear Engineering and Design, 2011, 241 (12): 4634-4642. Zhang Yapei, Qiu Suizheng, Su Guanghui, Tian Wenxi. Design and transient analyses of emergency passive residual heat removal system of CPR1000. Part I: Air cooling condition[J]. Progress in Nuclear Energy, 2011, 53:471-479. Zhang Yapei, Qiu Suizheng, Su Guanghui, Tian Wenxi. Design and transient analyses of emergency passive residual heat removal system of CPR1000[J]. Nuclear Engineering and Design, 2012, 242:247-256. Zhang Yapei, Su Guanghui, Qiu Suizheng, Tian Wenxi, Gaus-Liu Xiaoyang, Kretzschmar Frank, Miassoedov Alexi. A simple novel and fast computational model for the LIVE-L4[J]. Progress in Nuclear Energy, 2013, 68: 20-30.(SCI: 218TT ) Zhang Yapei, Su Guanghui, Qiu Suizheng, Tian Wenxi, Gaus-Liu Xiaoyang, Kretzschmar Frank, Miassoedov Alexi. Numerical study on the heat transfer characteristics of LIVE-L4 melt pool with a partial solidification process[J]. Progress in Nuclear Energy, 2014, 74: 213-221. (SCI: AI6VU ) Y. P. Zhang, S. P. Niu, L. T. Zhang, S. Z. Qiu, G. H. Su, W. X. Tian. A Review on Analysis of LWR Severe Accident. ASME J of Nuclear Rad Sci 1(4), 2015. Y.P. Zhang, L.T. Zhang, Y.K. Zhou, W.X. Tian, S.Z. Qiu, G.H. Su, B. Zhao, Y.D. Yuan, R.B. Ma. Natural convection heat transfer test for in-vessel retention at prototypic Rayleigh numbers - Results of COPRA experiments. Progress in Nuclear Energy. 2016, Vol.86: 80–86. (SCI: CZ4ZM ) Y.P. Zhang, L.T. Zhang, Y.K. Zhou, W.X. Tian, S.Z. Qiu, G.H. Su, B. Zhao, Y.D. Yuan, R.B. Ma. The COPRA experiments on the in-vessel melt pool behavior in the RPV lower head. Annals of Nuclear Energy. 2016, Vol.89: 19–27. (SCI: DC8IO ) Y.P. Zhang, W.X. Tian, S.Z. Qiu, G.H.Su. Study effects of the kinetics of local composition diffusion on the melt pool coolability by developing a DBL-LIVE model. Progress in Nuclear Energy. 2016, Vol.90: 219–228. (SCI: DN1DR ) Keyou Mao, Jun Wang, Longze Li, Yapei Zhang*, Wenxi Tian, Guanghui Su, Suizheng Qiu, Michael L. Corradini. Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000. Progress in Nuclear Energy. 2015, 85: 352 - 365. (SCI: CU2JF ) Yu Hongxing, Zhang Yapei, Su Guanghui, Qiu Suizheng, Tian Wenxi. A theoretical CHF model for downward facing surfaces and gaps under saturated boiling[J]. International Journal of Multiphase Flow, 2012, 45: 30-39. Wang Jun, Zhang Yapei, Mao Keyou, Tian Wenxi, Su Guhui, Qiu Suizheng. MELCOR Simulation of Core Thermal Response during a Station Blackout Initiated Severe Accident in China Pressurized Reactor (CPR1000) [J]. Progress in Nuclear Energy, 2014, 81: 6-15. Li longze, Zhang Yapei, Tian Wenxi, Su Guanghui, Qiu Suizheng. MAAP5 simulation of the PWR severe accident induced by pressurizer safety valve stuck-open accident[J]. Progress in Nuclear Energy, 2014, 77: 141-151.

推荐链接
down
wechat
bug