A parametric study of graphite dust deposition on high-temperature gas-cooled reactor (HTGR) steam generator tube bundles

M Wei, Y Zhang, X Wu, L Sun - Annals of Nuclear Energy, 2019 - Elsevier
Accumulation of abraded graphite dust is a major concern during a potential accident in high-
temperature gas-cooled reactors (HTGR). AVR experiments indicated that it is of great safety …

Experimental research on the radioactive dust in the primary loop of HTR-10

F Xie, J Cao, X Feng, X Liu, J Tong, H Wang… - … Engineering and Design, 2017 - Elsevier
Presence of radioactive dust, and also potential for its release, are considered important
issues as regards the safety of high temperature gas cooled reactors, especially the pebble …

Simulations of the dust behavior in the sampling and dust filters in the primary loop of HTR-10

W Peng, Q Sun, F Xie, Y Jiang - Nuclear Engineering and Design, 2018 - Elsevier
The radioactive dust in the primary loop of high-temperature gas-cooled reactors (HTGRs) is
one of the key challenges to operational safety, particularly in the event of depressurization …

Study of the deposition of graphite dust in the inlet passageway of intermediate heat exchanger in VHTR

Q Sun, X Hai, K Wang, W Peng - Experimental and Computational …, 2019 - Springer
The impact of graphite dust on structural equipment is a potential safety hazard in HTGR.
The present study focuses on the graphite particle deposition process on the deflector in the …

Design of the process and effluent radiation monitoring system of HTR-PM

F Xie, W Li, Z Li, J Cao, H Li… - International …, 2016 - asmedigitalcollection.asme.org
The process and effluent radiation monitoring system can provide information about kinds of
the radionuclide and activity concentrations, which is indispensable, important, and peculiar …

Study of an identification method of the temperature measuring pebbles in the transition core of HTR-10

L Wei, T Ma, Y Zhang, F Xie, L Liu, X Fang, C Li, B Xia… - 2018 - inis.iaea.org
We proposed an identification method for the temperature measuring pebbles during the
discharge process in the transition core of the 10 MW high temperature gas-cooled test …

The Design of the Radioactive Graphite Dust Experimental System in the Primary Circuit of HTR-PM

F Xie, Y Liang, Y Pi, H Li, J Qu - 2014 - inis.iaea.org
It has been received wide attentions to investigate the radioactive graphite dust in the
primary circuit since it was thought to be related to the safety of the pebble bed high …

Design of the Gas Sampling and Analyzing System of HTR-PM

J Zhu, F Xie - International Conference on Nuclear …, 2017 - asmedigitalcollection.asme.org
The high temperature gas-cooled reactor pebbled-bed module (HTR-PM) which is a
modular high temperature gas-cooled reactor demonstration power plant, is characterized …

ICONE23-1479 THE RESEARCH PROGRESS ON THE RADIOACTIVE GRAPHITE DUST IN HTR-10

F XIE, J CAO, J TONG, L WEI, X LIU… - The Proceedings of the …, 2015 - jstage.jst.go.jp
In the high temperature gas-cooled reactors, the dust safety issues have been received wide
attentions, especially in the pebble bed reactors. Dust complicated the prediction of fission …