[1] | Qi Wei, Hu Xupeng, Lu Xingyan, Zhang Dazhi, Qu Ming. Research on the Application of SPDM System in the Simulation and Verification Platform of Nuclear Power Digital Design[J]. Nuclear Power Engineering, 2024, 45(S1): 52-57. doi: 10.13832/j.jnpe.2024.S1.0052 |
[2] | Xing Shuo, Pu Zengping, Zhang Kun, Jiao Yongjun, Dai Xun, He Liang. Study on Evaluation Method for Creep Performance of New Zirconium Alloy Cladding[J]. Nuclear Power Engineering, 2023, 44(4): 234-239. doi: 10.13832/j.jnpe.2023.04.0234 |
[3] | Wang Yinli, He Zhengxi, Bao Chao, Gao Zhiyu, Wu Wenchao, Luo Tingfang, Yu Heng, Luo Wei. Test and Verification for Digital Nuclear Instrumentation System Prototype on Reactor[J]. Nuclear Power Engineering, 2022, 43(2): 226-231. doi: 10.13832/j.jnpe.2022.02.0226 |
[4] | Wu Qiaofeng, Liu Hongchun, Sun Shiyan, Li Yu, Wang Lin, Zhang Junqi, Wu Kunren. Analysis on Deterministic Behavior Design of Safety Digital Instrumentation and Control System[J]. Nuclear Power Engineering, 2022, 43(2): 167-170. doi: 10.13832/j.jnpe.2022.02.0167 |
[5] | Zhang Weichuan, Zhao Hui, Qin Fan, Zhao Yang, Qing Xianguo, Chen Jie, He Xiaopeng. Application of HALT Test Method in Development of Digital Instrument and Control Equipment[J]. Nuclear Power Engineering, 2021, 42(S2): 99-103. doi: 10.13832/j.jnpe.2021.S2.0099 |
[6] | Liu Wei, Li Zhigang, Lu Qi, Du Sijia, Liu Yu, Deng Jian, Hu Ying. Development and Validation of Integrate CHF Correlation Development System[J]. Nuclear Power Engineering, 2021, 42(3): 14-17. doi: 10.13832/j.jnpe.2021.03.0014 |
[7] | Zhu Junzhi, Yang Jue, Wan Lei, Cui Jun, Liu Yongkang, Liu Qingsong. Application of Requirement Modeling in Nuclear Requirements Analysis[J]. Nuclear Power Engineering, 2020, 41(5): 104-109. |
[8] | Huang Hao, Xie Qin, Yu Tao, Xie Jinsen, Chen Zhenping, Hou Chen, Su Shi. Simulation Verification of SINBAD Shielding Benchmark Experiment[J]. Nuclear Power Engineering, 2020, 41(4): 170-173. |
[9] | Jiang Guojin, Li Fu, Sun Wei, Sun Yongbin, Mo Changyu. Reliability Design and Application of NPP Digital I&C System Based on PSA[J]. Nuclear Power Engineering, 2019, 40(2): 99-104. doi: 10.13832/j.jnpe.2019.02.0099 |
[10] | He Xiaoqiang, Yu Hongxing, Wang Jinyu, Jiang Guangming, Dang Gaojian. Model Verification of Al2O3 Nanofluid Critical Heat Flux Mechanism[J]. Nuclear Power Engineering, 2019, 40(2): 6-9. doi: 10.13832/j.jnpe.2019.02.0006 |
[11] | Fang Yu, Xiong Guohua, Ma Shu, Cai Yefa, Kuang Dejun, Peng Chao. Research on Digital Upgrade Verification Platform Scheme for Simulation Control System of Daya Bay Nuclear Power Station[J]. Nuclear Power Engineering, 2018, 39(3): 81-85. doi: 10.13832/j.jnpe.2018.03.0081 |
[12] | Chao Fei, Shan Jianqiang, Zhang Yong, Wu Pan, Gou Junli, Li Jian. Study on Semi-Implicit Scheme for Two-Fluid Seven-Equation Two-Pressure Model[J]. Nuclear Power Engineering, 2018, 39(2): 142-148. doi: 10.13832/j.jnpe.2018.01.0142 |
[13] | Wang Chao, Yang Shuoyan, Peng Sitao, Li Guoren, Ma Yunfan, Chen Jun, Wang Junling, Lu Haoliang. Automated Validation of CGN Nuclear Software Package PCM[J]. Nuclear Power Engineering, 2018, 39(S2): 43-46. doi: 10.13832/j.jnpe.2018.S2.0043 |
[14] | Liu Ying, Yang Ming. Evaluation of Nuclear Safety-Critical Software Reliability of DCS[J]. Nuclear Power Engineering, 2016, 37(1): 143-147. doi: 10.13832/j.jnpe.2016.01.0143 |
[15] | Li Xingzhao, Li Pengzhou, Sun Lei. Decoupling Solution and Verification of Free Vibration Equation of Curved Beam[J]. Nuclear Power Engineering, 2016, 37(S2): 7-10. doi: 10.13832/j.jnpe.2016.S2.0007 |
[16] | Shao Changlei, Yin Junlian, He Xiaoming. Parametric Modeling of Refueling Operations for Pressurized Water Reactor Nuclear Power Plants[J]. Nuclear Power Engineering, 2016, 37(6): 125-129. doi: 10.13832/j.jnpe.2016.06.0125 |
[17] | Yang Ming, Song Mengchu. Study on Quantitative Software Reliability for Digital Control System[J]. Nuclear Power Engineering, 2014, 35(S1): 54-58. |
[18] | Yang Xiaohua, Liu Chaohui, Chen Zhi, Liu Jie, Wu Zhiqiang. A Merged-System-Status Monitoring Mechanism in NPP Digital Control System[J]. Nuclear Power Engineering, 2014, 35(3): 138-141. doi: 10.13832/j.jnpe.2014.03.0138 |
[19] | LI Meng, BAI Zhongxiong, XIANG Weiling, LU Yi, JIANG Zhiguo, YE Cenming, ZHANG Yi, RONG Ru. Development of Digital Instrument and Control System on Fast Neutron Critical Assembly[J]. Nuclear Power Engineering, 2012, 33(5): 100-106. |
[20] | YAO Qixin, HE Xuedong. Design of Control System for Test Platform of Reactor Shutdown System’s Ball Dropping Valve[J]. Nuclear Power Engineering, 2011, 32(2): 116-119,131. |