期刊创办：钱三强
刊名题字：郭沫若
期刊创办：钱三强
刊名题字：郭沫若
| Citation: |
THE STANDARD FACILITY FOR NUCLINDE ACTIVITY MEASUREMENT BY 4πγ HIGH PRESSURE IONIZATION CHAMBER[J]. Atomic Energy Science and Technology, 1994, 28(2): 189-191. DOI: 10.7538/yzk.1994.28.02.0189
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| [1] | HE Fan, CAI Xiangzhou, GUO Wei, HE Long, CUI Lei, ZHAO Heng. Development of Coupled Program Based on RELAP5/FLUENT[J]. Atomic Energy Science and Technology, 2021, 55(4): 693-703. DOI: 10.7538/yzk.2020.youxian.0325 |
| [2] | SONG Jian, TAN Chao, TANG Si-miao, LIU Li-min, TIAN Wen-xi, WU Ying-wei, QIU Sui-zheng, SU Guang-hui. Development and Verification of Thermal-hydraulic System Analysis Code Based on RELAP5 MOD3.2 for SFRs[J]. Atomic Energy Science and Technology, 2017, 51(6): 994-1001. DOI: 10.7538/yzk.2017.51.06.0994 |
| [3] | CHEN Yu-qing, YANG Lei, LIU Jun-teng. Sensitivity Analysis of Ship Reactor Compartment Model During LOCA[J]. Atomic Energy Science and Technology, 2014, 48(增刊1): 376-380. DOI: 10.7538/yzk.2014.48.S0.0376 |
| [4] | CHEN Lei, YAN Chang-qi, WANG Jian-jun. Feasibility Test for Reactor Coolant System Optimized Design Scheme[J]. Atomic Energy Science and Technology, 2014, 48(12): 2326-2332. DOI: 10.7538/yzk.2014.48.12.2326 |
| [5] | LI Ya, CAO Xia-xin, WANG Kai-yuan, SUN Zhong-ning. Validation of RELAP5/MOD3.2 Code for Simulating Pool Boiling Heat Transfer Outside Vertical Tube Bundle[J]. Atomic Energy Science and Technology, 2014, 48(12): 2269-2273. DOI: 10.7538/yzk.2014.48.12.2269 |
| [6] | ZHU Xiao-tong, CAO Xia-xin, DING Ming, GAO Li, ZHENG Yun-tao. Validation of REALP5 Code for Simulation of Geyser Flow Instability Under Low Pressure Natural Circulation Condition[J]. Atomic Energy Science and Technology, 2014, 48(8): 1406-1410. DOI: 10.7538/yzk.2014.48.08.1406 |
| [7] | XU Cai-hong, SHI Guo-bao. Applicability Research of RELAP5/MOD3.3 for Small Break Loss of Coolant Accident of NPP With Passive Safety System[J]. Atomic Energy Science and Technology, 2014, 48(2): 291-297. DOI: 10.7538/yzk.2014.48.02.0291 |
| [8] | LIU Xin-kai, LIU Jian-ge, PENG Min-jun. Sensitivity Analysis of Once-Through Steam Generator Based on RELAP5 Code[J]. Atomic Energy Science and Technology, 2012, 46(9): 1088-1096. DOI: 10.7538/yzk.2012.46.09.1088 |
| [9] | LIU Yu, ZHANG Hong, JIA Bao-shan. Research on Coupling Between RELAP5 and CFX Codes[J]. Atomic Energy Science and Technology, 2010, 44(3): 304-308. DOI: 10.7538/yzk.2010.44.03.0304 |
| [10] | SUN JILIANG;YU ERJUN China Institute of Atomic Energy, P. O. Box 275, Beijing, 102413. MAIN STEAM LINE BREAK (MSLB) ACCIDENT ANALYSIS FOR QINSHAN NUCLEAR POWER PLANT (QNPP) WITH RELAP5/MOD2[J]. Atomic Energy Science and Technology, 1993, 27(4): 304-304. DOI: 10.7538/yzk.1993.27.04.0304 |
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