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Z.J. Chen

Researcher at University of Science and Technology of China

Publications -  23
Citations -  176

Z.J. Chen is an academic researcher from University of Science and Technology of China. The author has contributed to research in topics: Natural circulation & Coolant. The author has an hindex of 7, co-authored 23 publications receiving 145 citations. Previous affiliations of Z.J. Chen include Chinese Academy of Sciences.

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Conceptual design of a small modular natural circulation lead cooled fast reactor SNCLFR-100

TL;DR: In this article, the steady state thermal-hydraulic performance, mass flow distribution characteristics and sub-channel T/H features were analyzed and discussed, and two major accident scenarios including unprotected overpower transient (UTOP) and unprotected loss of heat sink transient (ULOHS) were selected for a first evaluation of its dynamic behavior.
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Coupling a CFD code with neutron kinetics and pin thermal models for nuclear reactor safety analyses

TL;DR: In this article, the authors developed a CFD/neutron kinetics coupled code named FLUENT/PK for nuclear reactor safety analyses by coupling the commercial CFD code with the point kinetics model (PKM) and the pin thermal model (PTM).
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Study of core flow distribution for small modular natural circulation lead or lead-alloy cooled fast reactors

TL;DR: In this article, a non-uniform heated parallel channel flow distribution calculation code was developed and the comparison study between the channel method and the CFD method was carried out to assess the exactness of the developed code.
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Strong electron-boson coupling effect in the infrared spectra of Tl 2 Ba 2 CaCu 2 O 8+δ

TL;DR: In this paper, the magnetic correlation of the Ni and Co films was investigated by element-specific domain images, and the Ni magnetization exhibits a continuous rotation in the spin reorientation transition (SRT) region and that the Ni SRT thickness oscillates with the Fe film thickness.
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Natural circulation characteristics analysis of a small modular natural circulation lead–bismuth eutectic cooled fast reactor

TL;DR: In this article, a CFD simulation was conducted to analyze the natural circulation characteristics of LFR-10 primary cooling system during nominal condition, the velocity and temperature distribution of the reactor pool were illustrated and discussed, the core flow distribution behavior was evaluated.