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    Nodal code development for pressurized water reactor transient analysis based on non-linear iteration method
    Zheng Youqi, Lee Deokjung
    2017, 29: 036001. DOI: 10.11884/HPLPB201729.160297
    Abstract PDF
    Depletion chain compression method via quantitative significance analysis
    Huang Kai, Wu Hongchun, Li Yunzhao, Cao Liangzhi
    2017, 29: 036002. DOI: 10.11884/HPLPB201729.160302
    Abstract PDF
    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
    2017, 29: 036003. DOI: 10.11884/HPLPB201729.160286
    Abstract PDF
    Sensitivity analysis of nuclear data in core critical calculation of Qinshan Ⅱ
    Qiang Shenglong, Yin Qiang, Lu Wei, Li Qing, Chai Xiaoming
    2017, 29: 036004. DOI: 10.11884/HPLPB201729.160433
    Abstract PDF
    High burnup calculation characteristics of traveling wave reactor
    Sun Wei, Wei Yanqin, Wu Wenbin, Ni Dongyang, Lu Di, Lou Lei
    2017, 29: 036005. DOI: 10.11884/HPLPB201729.160339
    Abstract PDF
    Large-scale geometric modeling and management for reactor simulation
    Qin Guiming, Ma Yan, Fu Yuanguang, Li Gang, Deng Li,
    2017, 29: 036006. DOI: 10.11884/HPLPB201729.160357
    Abstract PDF
    Coupling of Monte-Carlo code JMCT and sub-channel thermal-hydraulics code COBRA-EN
    Shi Dunfu, Li Kang, Qin Guiming, Liu Xiongguo
    2017, 29: 036007. DOI: 10.11884/HPLPB201729.160383
    Abstract PDF
    Neutron flux calculation of reactor pressure vessel for MOX fuel core
    Wang Mengqi, Ding Qianxue, Mei Qiliang
    2017, 29: 036008. DOI: 10.11884/HPLPB201729.160179
    Abstract PDF
    Physics start-up analysis system
    Yu Chao, Fu Xuefeng, Li Wei, Wang Yangyi, Peng Sitao, Li Yiming, Cai Dechang,
    2017, 29: 036009. DOI: 10.11884/HPLPB201729.160294
    Abstract PDF
    Fuel loading pattern with 50% MOX fuel in HPR1000 core
    Liu Guoming, Guo Zhipeng
    2017, 29: 036010. DOI: 10.11884/HPLPB201729.160376
    Abstract PDF
    Overheating study in power plant control rod banks calibration test
    Wang Xinxin, Fu Xuefeng, Zhang Ming
    2017, 29: 036011. DOI: 10.11884/HPLPB201729.160172
    Abstract PDF
    Simulating plutonium isotopic composition in spent fuel
    Xu Xuefeng, Tian Dongfeng, Zhu Jianyu, Wu Jun, Shi Xueming
    2017, 29: 036012. DOI: 10.11884/HPLPB201729.160338
    Abstract PDF
    Three-dimensional distribution calculation for ex-core detector response functions
    Ding Qianxue, Mei Qiliang
    2017, 29: 036013. DOI: 10.11884/HPLPB201729.160191
    Abstract PDF
    Optimization research on gray control rod worth for control capability of mechanical shim operation strategy
    Dang Halei, Ye Qing, Yang Bo
    2017, 29: 036014. DOI: 10.11884/HPLPB201729.160298
    Abstract PDF
    Verification of CAACS program based on the critical accidents
    Yu Miao, Yi Xuan, Liu Guoming, Huo Xiaodong, Yang Haifeng
    2017, 29: 036015. DOI: 10.11884/HPLPB201729.160189
    Abstract PDF
    Transmutation characteristics of minor actinides in advanced pressurized water reactors
    Hu Wenchao, Jing Jianping, Pan Xinyi, Bi Jinsheng, Zhao Chuanqi, Zhang Chunming, Ouyang Xiaoping, Liu Bin
    2017, 29: 036016. DOI: 10.11884/HPLPB201729.160355
    Abstract PDF
    Simulation of JMCT based on JLAMT visualized modeling tool
    Zheng Yu, Quan Guoping, Li Gang
    2017, 29: 036017. DOI: 10.11884/HPLPB201628.160291
    Abstract PDF
    Application of improved transmutation trajectory analysis in neutron activation calculation
    Peng Yi, Zhang Jingyu, Chen Yixue
    2017, 29: 036018. DOI: 10.11884/HPLPB201729.160194
    Abstract PDF
    Conceptual neutronic design of conventional fast reactor with super high burnup
    Wang Xinzhe, Xu Li, Jia Xiaochun, Hu Yun
    2017, 29: 036019. DOI: 10.11884/HPLPB201729.160399
    Abstract PDF
    Shielding calculations of PWR using JSNT code
    Zhang Guangchun, Cheng Tangpei, Deng li, Zheng Zheng, Wang Chenlin
    2017, 29: 036020. DOI: 10.11884/HPLPB201729.160400
    Abstract PDF
    Thermal scattering data processing and development of Thermc module
    Li Wanlin, Wang Kan, Yu Ganglin
    2017, 29: 036021. DOI: 10.11884/HPLPB201729.160326
    Abstract PDF
    MOC/SN coupled 3D neutron transport software KYCORE
    Tang Xiao, Li Qing, Chai Xiaoming, Tu Xiaolan, Wang Kan
    2017, 29: 036022. DOI: 10.11884/HPLPB201729.160192
    Abstract PDF
    Calculation and verification of secondary neutron source intensity of nuclear reactor
    Su Genghua, Bao Pengfei, Han Song
    2017, 29: 036023. DOI: 10.11884/HPLPB201729.160186
    Abstract PDF
    Application of Jacobian-free Newton-Krylov method for high temperature reactor neutron diffusion equation calculation
    Lu Jia’nan, Guo Jiong, Li Fu
    2017, 29: 036024. DOI: 10.11884/HPLPB201729.160333
    Abstract PDF
    Testing and analysis of coupled program of MCNP and FISPACT
    Zhang Haoran, Zeng Qin, Chen Chong, Li Wei, Chen Hongli
    2017, 29: 036025. DOI: 10.11884/HPLPB201729.160424
    Abstract PDF