Zobrazeno 1 - 10
of 37
pro vyhledávání: '"Dazhi Qian"'
Autor:
Simao Guo, Xiaoyu Guo, Guanbo Wang, Yuchuan Guo, Zi Wang, Jun Leng, Wankui Yang, Bin Tang, Yaoguang Liu, Dazhi Qian
Publikováno v:
International Journal of Advanced Nuclear Reactor Design and Technology, Vol 5, Iss 4, Pp 168-188 (2023)
In order to meet realistic requirements for flexible and reliable power supply in special scenarios such as remote areas and deep ocean exploration, a novel megawatt portable nuclear power system called SUPERHERO (SUPERcritical carbon dioxide cycle-H
Externí odkaz:
https://doaj.org/article/c93327ac917d440dbb79d7fc764f87b5
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 4, Pp 734-743 (2017)
In order to investigate the swelling behavior and fuel–cladding interaction mechanism of U–10Zr alloy metallic fuel at very low burnup, an irradiation experiment was concisely designed and conducted on the China Mianyang Research Reactor. Two typ
Externí odkaz:
https://doaj.org/article/a276556339dd4693b2a063cd63987fe4
Autor:
Linjie Zhao, Lei Yue, Jiamao Li, Chengjian Xiao, Xin Yang, Rundong Li, Guanbo Wang, Xu Zhou, Yong Yang, Zhilin Chen, Mao Yang, Yu Gong, Guangming Ran, Xiaojun Chen, Chao Chen, Jingwei Hou, Heyi Wang, Dazhi Qian, Shuming Peng, Xinggui Long
Publikováno v:
Fusion Engineering and Design. 194:113732
Autor:
Baoxin Yuan, Herong Zeng, Wankui Yang, Jian Wang, Jie Zheng, Huan Huang, Songbao Zhang, Dazhi Qian
Publikováno v:
Progress in Nuclear Energy. 160:104683
Publikováno v:
Chinese Science Bulletin. 65:3526-3537
Medical radioisotopes as the cornerstone of modern nuclear medicine play an irreplaceable role in diagnostic imaging and therapy of various diseases, like malignant tumors, cardiovascular and brain disorders, according to achieve molecular level imag
Publikováno v:
Annals of Nuclear Energy. 130:124-130
The China Mianyang Research Reactor (CMRR), with a thermal power of 20 MW, is an important high performance research reactor operated in China. In this paper, we introduced the fuel management (FM) computation toolbox and confirmatory experiments per
Publikováno v:
Annals of Nuclear Energy. 122:125-136
The main purpose of the paper is to execute the thermal-hydraulic analysis of flow blockage in a single fuel assembly in the JRR-3M research reactor (Upgraded Japan Research Reactor No. 3). Using the one-dimensional system analysis code RELAP5/MOD3.4
Publikováno v:
Chinese Journal of Engineering Science. 24:116
Autor:
Haojun Zhou, Wenfeng Liang, Jiang-Meng Wang, Shuo Chen, Qilin Xie, Dazhi Qian, Xiao-Qiang Fan
Publikováno v:
Nuclear Engineering and Design. 338:16-22
In this paper, the neutronic and thermoelastic behaviors of prompt supercritical bursts in the fast burst reactor are numerically studied by developing a 3D coupled multiphysics FEM (finite element method) code FBR-MPC based on the neutron transport