High Power Laser and Particle Beams 2017 Issue 3 Nodal code development for pressurized water reactor transient analysis based on non-linear iteration method

Nodal code development for pressurized water reactor transient analysis based on non-linear iteration method
Zheng Youqi;

..............page:1-6

Depletion chain compression method via quantitative significance analysis
Huang Kai;,Wu Hongchun;,Li Yunzhao;,Cao Liangzhi;

..............page:7-12

Meticulous modeling and verification on criticality calculation of BEAVRS benchmark by Monte-Carlo code cosRMC
Yao Yuan;,Ma Xubo;,Chen Yixue;,Hu Jiaju;,Gao Bin;,Yu Hui;

..............page:13-17

Sensitivity analysis of nuclear data in core critical calculation of Qinshan Ⅱ
Qiang Shenglong;,Yin Qiang;,Lu Wei;,Li Qing;,Chai Xiaoming;

..............page:18-22

High burnup calculation characteristics of traveling wave reactor
Sun Wei;,Wei Yanqin;,Wu Wenbin;,Ni Dongyang;,Lu Di;,Lou Lei;

..............page:23-27

Large-scale geometric modeling and management for reactor simulation
Qin Guiming;,Ma Yan;,Fu Yuanguang;,Li Gang;,Deng Li;

..............page:28-31

Coupling of Monte-Carlo code JMCT and sub-channel thermal-hydraulics code COBRA-EN
Shi Dunfu;,Li Kang;,Qin Guiming;,Liu Xiongguo;

..............page:32-38

Neutron flux calculation of reactor pressure vessel for MOX fuel core
Wang Mengqi;,Ding Qianxue;,Mei Qiliang;

..............page:39-43

Physics start-up analysis system
Yu Chao;,Fu Xuefeng;,Li Wei;,Wang Yangyi;,Peng Sitao;,Li Yiming;,Cai Dechang;

..............page:44-48

Fuel loading pattern with 50% MOX fuel in HPR1000 core
Liu Guoming;,Guo Zhipeng;

..............page:49-55

Overheating study in power plant control rod banks calibration test
Wang Xinxin;,Fu Xuefeng;,Zhang Ming;

..............page:56-59

Simulating plutonium isotopic composition in spent fuel
Xu Xuefeng;,Tian Dongfeng;,Zhu Jianyu;,Wu Jun;,Shi Xueming;

..............page:60-64

Three-dimensional distribution calculation for ex-core detector response functions
Ding Qianxue;,Mei Qiliang;

..............page:65-70

Optimization research on gray control rod worth for control capability of mechanical shim operation strategy
Dang Halei;,Ye Qing;,Yang Bo;

..............page:71-78

Verification of CAACS program based on the critical accidents
Yu Miao;,Yi Xuan;,Liu Guoming;,Huo Xiaodong;,Yang Haifeng;

..............page:79-83

Transmutation characteristics of minor actinides in advanced pressurized water reactors
hu wen chao ;, jing jian ping ;, pan zuo zuo ;, bi jin sheng ;, zhao chuan qi ;, zhang chun ming ;, ou yang xiao ping ;, liu bin ;

..............page:84-89

Simulation of JMCT based on JLAMT visualized modeling tool
Zheng Yu;,Quan Guoping;,Li Gang;

..............page:90-95

Application of improved transmutation traj ectory analysis in neutron activation calculation
Peng Yi;,Zhang Jingyu;,Chen Yixue;

..............page:96-101

Conceptual neutronic design of conventional fast reactor with super high burnup
Wang Xinzhe;,Xu Li;,Jia Xiaochun;,Hu Yun;

..............page:102-106

Shielding calculations of PWR using JSNT code
Zhang Guangchun;,Cheng Tangpei;,Deng li;,Zheng Zheng;,Wang Chenlin;

..............page:107-112

Thermal scattering data processing and development of Thermc module
Li Wanlin;,Wang Kan;,Yu Ganglin;

..............page:113-117

MOC/SN coupled 3D neutron transport software KYCORE
Tang Xiao;,Li Qing;,Chai Xiaoming;,Tu Xiaolan;,Wang Kan;

..............page:118-122

Calculation and verification of secondary neutron source intensity of nuclear reactor
Su Genghua;,Bao Pengfei;,Han Song;

..............page:123-126

Application of Jacobian-free Newton-Krylov method for high temperature reactor neutron diffusion equation calculation
Lu Jia'nan;,Guo Jiong;,Li Fu;

..............page:127-132

Testing and analysis of coupled program of MCNP and FISPACT
Zhang Haoran;,Zeng Qin;,Chen Chong;,Li Wei;,Chen Hongli;

..............page:133-140