论文期刊

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论文标题 作者 发表/完成日期 期刊名称
Robust control of once-through Canadian Supercritical Water-cooled Reactors Peiwei Sun, Ji Feng, Xianbao Yuan, Liang Zhao, Furong Liu 2017-06-16 Nuclear Technology
Control system design and validation platform development for small pressurized water reactors (SPWR) by coupling an engineering simulator and MATLAB/Simulink Peiwei Sun, Huanhuan Zhao, Longtao Liao, Jianmin Zhang, Guanghui Su 2017-04-01 Annals of Nuclear Energy
Control strategy study for once-through direct cycle Canadian SCWRs Peiwei Sun, Jianmin Zhang 2017-03-27 Progress in Nuclear Energy
Linear parameter-varying modeling and control of the steam temperature in a Canadian SCWR Peiwei Sun, Jianmin Zhang, Guanghui Su 2017-03-07 Nuclear Engineering and Design
Thermal-hydraulic Design and Analysis Code Development for Steam Generator of CFR600 Peiwei Sun, Zi Wang, Jianmin Zhang, Guanghui Su 2016-04-01 Annals of Nuclear Energy
Control of Canadian once-through direct cycle supercritical water-cooled reactors Peiwei Sun, Baosheng Wang, Jianmin Zhang, Guanghui Su 2015-07-01 Annals of Nuclear Energy
Decoupling Control of Canadian Supercritical Water-cooled Reactors Peiwei Sun, Jin Jiang, Kai Wang 2014-02-24 Nuclear Technology
Construction and Analysis of a Dynamic Model for a Canadian Direct-Cycle SCWR for Control System Studies Peiwei Sun, Jin Jiang 2012-11-26 Nuclear Technology
Construction of dynamic model of CANDU-SCWR using moving boundary method Peiwei Sun, Jin Jiang，Jianqiang Shan 2011-02-18 Nuclear Engineering and Design
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会议论文

 序号  作者  论文标题  ： 会议名称    时间                     

[1]Sun,P.W.,Jiang.J.,Zhang,J.M.,Modeling, Analysis of Nonlinearities of Canadian SCWR and their Gain Scheduling Control:The 6th International Symposium on Supercritical Water-cooled Reactors (ISSCWR-6),2013[C]

[2]Sun,P.W.,Zhang,J.M.,Hybrid Feedforward and Feedback Control of Steam Temperature in a Once-through Direct Cycle Canadian SCWR:21st International Conference on Nuclear Engineering (ICONE 21),2013[C]

[3]Sun,P.W.,LPV Modeling and Control of Canadian Supercritical Water-cooled Reactors:ISOFIC/ISSNP 2014,2014[C]

[4]Sun,P.W.,Zhang,J.M.,Nonlinearities analysis and self-scheduled Hinfinity control of steam temperature in a Canadian SCWR: 23st International Conference on Nuclear Engineering (ICONE23),2015[C]

[5]孙培伟,陈鹏,张建民,加拿大超临界水堆蒸汽温度的模糊PI控制:第三届中国（国际）核电仪控技术大会,2015[C]

Sun,P

[6]Sun,P.W.,Zhang,J.M.,Control of Canadian once through direct cycle supercritical water-cooled reactors:第三届中国（国际）核电仪控技术大会,2015[C]

[7]Wang,Z.,Sun,P.W.,Zhang,J.M.,Dynamic model development of a sodium-heated steam generator:PNBC2016,2016[C]

[8]Cao,H.S.,Sun.P.W.,Zhang.J.M.,Power optimization of steam generators under fault conditions:PNBC2016,2016[C]

[9]Feng,J.,Sun,P.W.,Yuan,X.B.,Li,F.R.,Robust feedforward and feedback control of the steam generaotor in a Canadian SCWR:PNBC2016[C]

[10]Wang,K.,Sun,P.W.,Xiong,Q.W.,Dynamic Modeling and Characteristics Analysis of NuScale:ISSNP2016和核反应堆系统设计技术重点实验室年会,2016[C]

[11]赵欢欢,孙培伟,陈鹏,基于压水堆核电厂仿真机的小型压水堆控制系统仿真研究基于压水堆核电厂仿真机的小型压水堆控制系统仿真研究: 第四届中国（国际）核电仪控技术大会,2017[C]

[12]Cao,H.S.,Sun,P.W.,  Simulation of small steam generator tube break (SSGTB) in a small pressurized water reactor(SPWR):25th International Conference on Nuclear Engineering(ICONE25),2017[C]

[13]Sun,P.W.,Zhao,H.H.,Zhang,J.M.,Small pressurized water reactor (SPWR) simulaiton platform development for its design verification:25th International Conference on Nuclear Engineering(ICONE25),2017[C]

[14]Wang,K.,Sun,P.W.,Control system design for nuscale:25th International Conference on Nuclear Engineering(ICONE25),2017[C]

[15]Zhang,X.S.,Sun,P.W.,Control system design of supercritical co2 direct cycle gas fast reactor:25th International Conference on Nuclear Engineering(ICONE25),2017[C]

[16]Sun,P.W.,Zhang,J.M.,Control system design for a small pressurized water reactor:10th International Embedded Topical Meeting on Nuclear Plant Instrumentation, Control & Human-Machine Interface Technologies (NPIC & HMIT 2017),2017[C]