Zhimin Dai

Prof. Dr. Zhimin Dai


Research Focus & Metrics

Academic Career Length

19Years (2008-Present)

(Calculated once Scilit publication data is synced: current year − year of first publication + 1)

Representative Publications

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14 November 2023 in Nuclear Science and Techniques
Verified
Journal Article
Closed access
PDF file
JLJia-Xin Li
Jia-Xin Li
HHHui-Liang Hou
Hui-Liang Hou
YHYue-Feng Huang
Yue-Feng Huang
MCMao-Song Cheng
Mao-Song Cheng
ZDZhimin Dai
Zhimin Dai

1 March 2011 in Chinese Physics C
Verified
Journal Article
Closed access
HDHai-Xiao Deng
Hai-Xiao Deng
TLTang-Yu Lin
Tang-Yu Lin
JYJun Yan
Jun Yan
DWDong Wang
Dong Wang
ZDZhimin Dai
Zhimin Dai
Laser-beam interaction in an undulator is commonly suggested in the development of free electron laser (FEL) schemes. In this paper, a three-dimensional algorithm is developed to assist in laser-beam interaction simulation in an undulator, which is built on the basis of the fundamentals of electrodynamics, i.e. the electron’s behavior is determined by the magnetic field and the laser electric field in the time domain. On the basis of the algorithm, the detuning effect in a laser heater, the carrier envelope phase effect of a few-cycle laser in attosecond X-ray FEL schemes and output wavelength tuning in a high gain harmonic generation FEL are numerically discussed.

14 October 2023 in Nuclear Engineering and Design
Verified
Journal Article
Closed access
TZTianze Zhou
Tianze Zhou
KYKaicheng Yu
Kaicheng Yu
MCMao-song Cheng
Mao-song Cheng
RLRui Li
Rui Li
ZDZhimin Dai
Zhimin Dai

31 January 2025 in Energies
Verified
Journal Article
Open access
PDF file
SCshichao chen
shichao chen
RLRui Li
Rui Li
XZXiandi Zuo
Xiandi Zuo
MCMao-song Cheng
Mao-song Cheng
ZDZhimin Dai
Zhimin Dai
The liquid-fueled molten salt reactor (MSR) is one of the candidate reactors for the Generation IV advanced nuclear power systems, which utilizes flowing liquid molten salt as both fuel and coolant. In transients of liquid-fueled MSRs, the distribution change in the delayed neutron precursors (DNPs) in the primary loop has an important impact on system safety analysis. In order to analyze and evaluate this effect, the RELAP5-TMSR code with a 1-D DNP transport model was used to model the Molten Salt Breeder Reactor (MSBR), and several representative transient scenarios, including the loss of primary flow, increase in primary flow, loss of secondary flow, reactivity perturbation, and load change, were simulated and analyzed. The results show that the DNP distribution changes obviously during primary flow transients, especially during the loss of primary flow. Besides, the power response trends at different power levels during the loss of primary flow are different. The analysis results reveal the steady-state and dynamic characteristics of the DNP distribution, indicating that the DNP distribution, temperature feedback, and reactor power are strongly coupled, which has significant implications for the design and safety analysis of liquid-fueled MSRs.

15 February 2025 in International Journal of Radiation Oncology - Biology - Physics (IJROBP)
Verified
Journal Article
Closed access
ZLZhiyuan Lin
Zhiyuan Lin
ZLZuokang Lin
Zuokang Lin
ZZZijian Zhang
Zijian Zhang
GWGuanchao Wu
Guanchao Wu
YZYinan Zhu
Yinan Zhu
ZDZhimin Dai
Zhimin Dai

1 February 2008 in Nuclear Science and Techniques
Verified
Journal Article
Closed access
HDHaixiao Deng
Haixiao Deng
ZDZhimin Dai
Zhimin Dai