Sep 2003 – Jun 2007, Xi'an Jiao Tong University, nuclear engineering and nuclear technology, BA.
Sep 2007 – Mar 2010, Shanghai Jiao Tong University, nuclear power science and engineering, MA.
Sep 2014 – Jun 2020, Shanghai Jiao Tong University, nuclear science and technology, PhD.

Jun 2010 – Oct 2020, State Nuclear Power Software Development Center/ State Power Investment Corporation Research Institute. The leader of thermal-hydraulic code development group and test group, director of Shanghai engineering application test center.

Thermal-hydraulic code development

1 National Science and Technology Major Project of the Ministry of Science and Technology of China. The development of nuclear power software (No. 2011ZX06004-024). The main participant.
2 National Science and Technology Major Project of the Ministry of Science and Technology of China. The assessment of nuclear power software (No. 2016ZX06004-002). In charge of one sub-sub-project.
3 National Science and Technology Major Project of the Ministry of Science and Technology of China. The third-party evaluation and supplementary experimental verification of nuclear power software (No. 2017ZX06004-002). In charge of one sub-project.
4 Regulatory Guide, The development and application of computer software for safety analysis. In charge of writing one chapter.
5 OECD/NEA PKL Phase 4 PROJECT. The member of Programm Review Group and Management Board.
6 The certification of COSINE codes. In charge two codes' certification.

1 Zhang H., Yang Y. Development of a Riemann solver for the two-fluid seven-equation model[J]. Annals of Nuclear Energy, 2020, 142: 107391. https://doi.org/10.1016/j.anucene.2020.107391.
2 Zhang H., Yang Y. A split scheme for the two-fluid seven-equation model with source terms[J]. Progress in Nuclear Energy, 2020, 124: 103350. https://doi.org/10.1016/j.pnucene.2020.103350.
3 Zhang H., Yang Y. Development of a solver for multi-fluid and multi-pressure model[J]. Nuclear Science and Engineering, 2019, 193: 283-298. https://doi.org/10.1080/00295639.2018.1512788.
4 Zhao X., Cao Y., Lin M., Zhang H., Yang Y. Adaptive mesh method applied to the thermal hydraulic program of system code with a judging criterion based on the matrix error[J]. Annals of Nuclear Energy, 2018, 120:723-734. https://doi.org/10.1016/j.anucene.2018.06.040.
5 Yang Y., Zhang H. Challenges on innovations of newly-developed safety analysis codes[J]. Kerntechnik. 2016, 81: 117-120. https://doi.org/10.3139/124.110699.
6 Zhang G., Zhang H , Gu H., et al. Experimental and numerical investigation of turbulent convective heat transfer deterioration of supercritical water in vertical tube[J]. Nuclear Engineering and Design, 2012, 248: 226-237. https://doi.org/10.1016/j.nucengdes.2012.03.026.
7 沙會娥, 張昊, 吳照國, 等. 基于動力學(xué)原理的cosFlow軟件主泵模塊研發(fā)及驗證[J]. 核科學(xué)與工程, 2018, 38: 141-147.
8 張昊, 楊燕華. 高階離散格式在兩流體模型中的初步應(yīng)用研究[J]. 核動力工程, 2017, 38: 29-33.
9 蔡溢, 林萌, 張昊, 等. 反應(yīng)堆熱工安全分析程序相間摩擦模型開發(fā)測試[J]. 核技術(shù), 2014, 37:76-80.
10 張戈, 張昊, 顧漢洋, 等. 10mm垂直單管通道內(nèi)超臨界水傳熱弱化現(xiàn)象的實驗與數(shù)值分析[J]. 原子能科學(xué)技術(shù), 2014, 48:630-636.
11 張昊, 謝正瑞, 楊燕華. 強(qiáng)浮升力作用下超臨界流體對流換熱的湍流模型研究[J]. 核動力工程, 2011, 32: 63-69.
12 Zhang H., Yang Y. A study on high order discrete scheme for two-fluid model. 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics. Xi’an, China, September 3-8, 2017: No. 20623.
13 Sha H., Zhang H., Du Z., et al. Verification of Accumulator Model in COSINE. Proceedings of the 2013 21st International Conference on Nuclear Engineering. Chengdu, China, July 29-August 2, 2013: ICONE21-15639.
14 Zhang H., Xie Z., Yang Y. Numerical Study on Supercritical Fluids Flow and Heat Transfer under Buoyancy. The 8th International Topical Meeting on Nuclear Thermal-hydraulics, Operation and Safety. Shanghai, China, October 10-14, 2010: N8P0187.
15 Zhang H., Xie Z., Yang Y. Numerical study on strong heating internal flow and acceleration effect. The Fourth Korea-China Workshop on Nuclear Reactor Thermal Hydraulics. Jeju Island, Korea, May 19-20, 2009: C-023.
16 張昊, 吳照國, 龔湛, 林萌, 楊燕華, 沈峰. COSINE程序水力學(xué)方程的測試方法. 第十三屆全國反應(yīng)堆熱工流體學(xué)術(shù)會議. 上海, 2013年11月3日-6日.
17 張昊, 楊燕華, 謝正瑞. 超臨界壓力下流動傳熱的低雷諾數(shù)湍流模型研究. 2008年中國工程熱物理學(xué)會多相流年會. 2008.

1 China Nuclear Energy Association Science and Technology Award. Third-class, 2018, NO.2018HNJ79R-03.
2 National Electric Power Workers Technology Award. 2018, 20180548.
3 State Power Investment Corporation Science and Technology Progress Award. Second-class, 2019, SPIC-KJ-2018-012-R03.
4 State Power Investment Corporation Science and Technology Progress Award. Third-class, 2019, SPIC-KJ-2018-032-R03.
5 State Nuclear Power Technology Corporation Technology Award. Second-class, 2015, GH-JM-2014-008-R03.