Experimental study on cryogenic adsorption of methane by activated carbon for helium coolant purification of High-Temperature Gas-cooled Reactor

2017 ◽  
Vol 101 ◽  
pp. 367-374 ◽  
Author(s):  
Hua Chang ◽  
Zong-Xin Wu ◽  
Hai-Jun Jia
2015 ◽  
Vol 93 ◽  
pp. 576-583 ◽  
Author(s):  
P. Fayzi ◽  
A. Mirvakili ◽  
M.R. Rahimpour ◽  
M. Farsi ◽  
A. Jahanmiri

1986 ◽  
Vol 60 (4) ◽  
pp. 287-290 ◽  
Author(s):  
A. V. Varezhkin ◽  
Ya. D. Zel'venskii ◽  
I. V. Metlik ◽  
A. A. Khrulev ◽  
A. N. Fedoseenkov

Author(s):  
Yang Liu ◽  
Ximing Sun ◽  
Yujie Dong

In the high temperature gas-cooled reactor, the oxidation of graphite is inevitable as a result of impurities in helium coolant. As an air or water ingress accident would cause graphite components to oxidize more seriously, thereby it would affect the reactor normal operation and safety. Oxidation velocity and oxidation product of a selected graphite (excess material from 10MW High Temperature Gas-cooled Reactor) were studied, samples are oxidized between 400°C to 1200 °C with gas flow rates ranging from 125 to 500 ml/min. Relationship between oxidation conditions and surface properties of oxidized graphite is also elaborated by means of gas chromatography and scanning electron microscopy for scanning of graphite surface.


Energy ◽  
2019 ◽  
Vol 180 ◽  
pp. 61-78 ◽  
Author(s):  
Thibaut Esence ◽  
Tristan Desrues ◽  
Jean-François Fourmigué ◽  
Grégory Cwicklinski ◽  
Arnaud Bruch ◽  
...  

2015 ◽  
Vol 1084 ◽  
pp. 313-316
Author(s):  
Denis F. Baybakov ◽  
Aleksey V. Golovatsky ◽  
Artem G. Naymushin ◽  
Vladimir N. Nesterov ◽  
Savva N. Savanyuk ◽  
...  

This paper describes a method of determining the correlation of the exhausted graphite fuel blocks’ lifespan in high temperature gas-cooled reactors with the fuel burnup. The axial distribution of the local values of the exhausted lifespan of graphite fuel blocks was obtained. It is shown that for ensuring the compliance of the design value of the fuel burnup with graphite fuel blocks operability, it is necessary to reduce the average mixed temperature of the helium coolant leaving the reactor core and as well as reduce the time between nuclear fuel recharges.


1988 ◽  
Vol 64 (6) ◽  
pp. 508-510
Author(s):  
A. V. Varezhkin ◽  
Ya. D. Zel'venskii ◽  
A. A. Khrulev ◽  
A. N. Fedoseenkov

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