桂民洋

桂民洋，男，硕士生导师，主要研究方向为反应堆热工水力多尺度数值模拟（包括系统分析、精细子通道分析和三维CFD分析），临界热流密度机理模型开发，海洋条件热工水力特性等。主持或参与国家自然科学基金、国家科技重大专项课题、上海728研究院和中国核动力研究设计院等多项课题研究。已发表论文20余篇，其中SCI检索12篇，EI检索2篇，获发明专利2项，软件著作权1项。目前担任《Progress in Nuclear Energy》、《Annals of Nuclear Energy》、《Front. in Nucl. Eng.-Fission and Reactor Desg.》等行业期刊审稿人。

2016.09-2022.06：西安交通大学-核科学与技术-硕博连读（导师：田文喜教授）

2012.08-2016.06：哈尔滨工程大学-核科学与核技术-本科

田文喜, 桂民洋, 张魁, 章静, 秋穗正, 苏光辉. 一种竖直棒束通道底部进口两相泡状流搅混装置及方法[P]. 中国：CN109675476B, 2020-05-15.
王成龙, 吴迪, 桂民洋, 张大林, 田文喜, 秋穗正, 苏光辉. 一种液态金属冷却绕丝定位熔盐堆堆芯[P]. 中国：CN112349436B, 2021-10-19.

Sun RY, Gui MY, Wang JS, et al. SACOS-PLATE: A new thermal-hydraulic subchannel analysis code for plate type fuel assemblies[J]. Annals of Nuclear Energy, 2024, 204: 110517.

Wu D, Gui MY*, Cheng J, et al. Condensation enhancement experiment investigation of pure steam and steam-air mixture over the chrome-plated tube with different plating thickness[J]. Progress in Nuclear Energy, 2023, 166: 104971.
Ning K, He Y, Zhao F, Dong X, Gui MY, Sun R*, & Tan S*. Numerical investigation on flow and heat transfer characteristics of helium–xenon gas mixture in rod bundles[J]. Progress in Nuclear Energy, 2023, 166, 104947.

Gui MY, Tian WX*, Wu D, et al. Development of a two-fluid based thermal-hydraulic subchannel analysis code with high-resolution numerical method[J]. Progress in Nuclear Energy, 2021, 134: 103671. (SCI: 000634783800003; EI: 20210609894860).
Gui MY, Tian WX*, Wu D, et al. Parallelization and application of SACOS for whole core thermal-hydraulic analysis[J]. Nuclear Engineering and Technology, 2021. (SCI: 000697930900004).

Tian WX*, Gui MY, Wu D, et al. Study on flow instability in natural circulation loop with parallel channels under moving condition[J]. Nuclear Engineering and Design, 2021, 379(3):111246. (SCI: 000512220900029; EI: 20210609894860).

Wang CL†, Wu D†, Gui MY, et al. Flow blockage analysis for fuel assembly in a lead-based fast reactor[J]. Nuclear Engineering and Technology, 2021. (SCI: 000687132200010).
桂民洋, 田文喜*, 吴迪, 等. 棒束子通道CHF机理模型开发及初步验证[J]. 原子能科学技术, 2021, 55(11):9. (EI: 20214611143675).

Gui MY, Tian WX*, Wu D, et al. Study on CHF characteristics in narrow rectangular channel under complex motion condition[J]. Applied Thermal Engineering, 2020, 166: 114629. (SCI: 000512220900029; EI: 20194807747582).

Gui MY, Tian WX*, Wu D, et al. Review of the AFD-type CHF mechanistic model and its application to rod bundle[J]. Progress in Nuclear Energy, 2020, 119: 103168. (SCI: 000508745700002; EI: 20193907476593).

Gui MY, Tian WX*, Wu D, et al. Development of a three-field mechanistic model for dryout prediction in annular flow[J]. Annals of Nuclear Energy, 2020, 135: 106978. (SCI: 000496898500041; EI: 20193407344203).

Gui MY, Tian WX*, Wu D, et al. Program development and preliminary CHF characteristics analysis for natural circulation loop under moving condition[J]. Nuclear Engineering and Technology, 2020. (SCI: 000636560800011).

Wu D, Gui MY, Sun H, et al. Preliminary neutronic/ thermal-hydraulic evaluation and safety system optimization of PWR loaded with fully ceramic microencapsulated fuel[J]. Progress in Nuclear Energy, 2020, 122: 103261. (SCI: 000525863200004; EI: 20200508117970).
Wu D, Gui MY, Zhang R, et al. Preliminary optimization of emergency core cooling system with accident-tolerant fuels[J]. Annals of Nuclear Energy, 2020, 142: 107411. (SCI: 000526111700038; EI: 20200908236709).
Wu D, Wang CL, Gui MY, et al. Improvement and validation of a sub-channel analysis code for a lead-cooled reactor with wire spacers[J]. International Journal of Energy Research, 2020. (SCI: 000577703000001; EI: 20204209361593).
张焱,  桂民洋, 李杨柳, 等. 深水池式低温供热堆堆芯子通道程序改进与计算分析[J]. 核科学与工程, 2020, 40(4):8.

Wu D, Gui MY, Zhang J, et al. Code development and characteristics analysis for Leak Before Break in the pipelines of Sodium-cooled Fast Reactor[J]. Annals of Nuclear Energy, 2019: 777~794. (SCI: 000484649800075; EI: 20192907205037).

桂民洋, 田文喜, 吴迪, 等. 子通道程序与CFD程序的耦合方法研究[J], 原子能科学技术, 2018, 052(011): 1962~1967. (EI: 20190206369969).

Gui MY, Wu D, Tan SC, Tian WX. Study on Dryout-type CHF Characteristics under Complex Motion Condition[C]. 10th Korea-China Workshop on Nuclear Reactor Thermal-Hydraulics (WORTH-10), Jeju, Korea, November 26~29, 2023.

Gui MY, Tian WX, Wu D, et al. Development and Preliminary Application of the Two-Fluid Subchannel Analysis Code SACOS2.0[C]. 12th Joint International Symposium on Nuclear Science and Technology, UT-XJTU-SJTU joint Workshop, Shanghai, China, Dec. 1-4, 2019.
Gui MY, Tian WX, Wu D, et al. Theoretical investigation on CHF characteristics of natural circulation under moving condition[C]. International Topical Meeting on Advances in Thermal Hydraulics, Paris, France, Mar. 31~Apr. 3, 2020.
桂民洋, 刘镝, 田文喜, 等. 基于VIPRE的运动条件下子通道程序开发[C]. 第十五届全国反应堆热工流体学术年会, 荣成, 2017.
桂民洋, 吴迪, 田文喜, 等. 临界热流密度机理模型在棒束子通道中的应用[C]. 2018国家能源核电软件重点实验室学术交流会暨学术年会, 重庆, 2018.
桂民洋, 田文喜, 吴迪, 等. 两流体子通道分析程序SACOS2.0的开发及初步验证[C]. 第十六届全国反应堆热工流体学术会议暨中核核反应堆热工水力技术重点实验室2019年学术年会, 惠州, 2019.
桂民洋, 田文喜, 吴迪, 等. 堆芯范围内多物理多尺度耦合技术初步研究[C]. 核反应堆系统设计技术国家级重点实验室学术委员会三届四次会议暨2019年度学术年会, 成都, 2019.

桂民洋, 田文喜, 吴迪, 等. 子通道程序SACOS在全堆芯热工水力分析中的应用[C]. 2020国家能源核电软件重点实验室学术交流会暨学术年会, 哈尔滨, 2020.