A review of HTGR graphite dust transport research

Q Sun, W Peng, S Yu, K Wang - Nuclear Engineering and Design, 2020 - Elsevier
Graphite dust is the important contents of source term for safety analysis of high temperature
gas-cooled reactors (HTGR). The spherical fuel element circulation in a pebble bed reactor …

An experimental study on the wall collision of micro-sized graphite particles by high-speed photomicrography

Y Zhang, Z Fang, S Zhao, M Wei, X Wu… - Progress in Nuclear Energy, 2020 - Elsevier
The micro-sized graphite dust plays an important role in pebble-bed high temperature gas-
cooled reactors, for the close relation with the fission products (FPs). However, an accurate …

An experimental investigation on the settling velocity and drag coefficient of micrometer-sized natural, IG-110, NG-CT-10 and A3-3 graphite particles

Z Fang, Y Zhang, S Zhao, X Li, X Wu, L Sun - Journal of Aerosol Science, 2021 - Elsevier
Micrometer-sized graphite particles are widely found in nature and industry. Particularly, the
graphite dust is an important problem for the pebble-bed high temperature gas-cooled …

Transport and deposition behaviors of graphite aerosol in the steam generator building during an overpressure discharge accident of HTR-PM

Z Fang, X Liu, Y Zhang, Y Wang, Z You, L Sun… - Nuclear Engineering and …, 2023 - Elsevier
The water-ingress accident is one of design basis accidents of high-temperature gas-cooled
reactors (HTGR). The rapid change of the flow field and the direct brush of the high-velocity …

Numerical predictions of the drag coefficients of irregular particles in an HTGR

Q Sun, G Zhao, W Peng, J Wang, Y Jiang, S Yu - Annals of Nuclear Energy, 2018 - Elsevier
The present study analyzed the drag coefficient of simplified graphite dust particles in an
HTGR using a computational fluid dynamics (CFD) model. The effects of the particle …

A comprehensive study on source terms in irradiated graphite spheres of HTR-10

F Xie, H Li, X Liu, J Chen, C Li, X Chen… - Annals of Nuclear …, 2018 - Elsevier
With previously developed experimental methods which include the preparation and
measurement process for the graphite sample, two new irradiated graphite spheres with …

Study of tritium in the primary loop of HTR-10: Experiment and theoretical calculations

F Xie, J Cao, X Feng, J Tong, Y Dong, Z Zhang… - Progress in Nuclear …, 2018 - Elsevier
An experimental system for the measurement of tritium in the primary loop of HTR-10 has
been established, sampling gas from the helium purification system. After the restart of HTR …

Study of the behavior of dust particles in helium turbines considering the effects of particle deposition and resuspension

X Wang, Q Sun, X Yang, Y Zhu, P Jiang, W Peng - Powder Technology, 2024 - Elsevier
The deposition of graphite dust poses significant challenges to the helium turbines in high-
temperature gas-cooled reactors. In this study, FLUENT, a Computational Fluid Dynamics …

Graphite aerosol release to the containment in a water ingress accident of high temperature gas-cooled reactor (HTGR)

M Wei, Y Zhang, Z Fang, X Wu, L Sun - Nuclear Engineering and Design, 2019 - Elsevier
As a design-basis accident, the water ingress due to the rupture of a single steam generator
tube is a major threat for high-temperature gas-cooled reactors (HTGR). The rapid rise of …

The critical sticking velocity of non-spherical graphite particles: a numerical study and validation

Z Fang, Y Zhang, M Wei, S Zhao, L Sun… - Nuclear Engineering and …, 2020 - Elsevier
For high temperature gas-cooled reactors (HTGR), the accumulation of the micro-sized
graphite dust in the primary loop is a major concern during a potential accident such as the …