CaEH-4B zeolite used to remove carbon dioxide from the helium coolant in a high-temperature gas-cooled reactor

1988 ◽  
Vol 64 (6) ◽  
pp. 508-510
Author(s):  
A. V. Varezhkin ◽  
Ya. D. Zel'venskii ◽  
A. A. Khrulev ◽  
A. N. Fedoseenkov
Keyword(s):  
Carbon Dioxide ◽  
High Temperature ◽  
Helium Coolant ◽  
High Temperature Gas

Adsorption removal of carbon dioxide from the helium coolant of high-temperature gas-cooled reactors

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
Keyword(s):  
Carbon Dioxide ◽  
High Temperature ◽  
Adsorption Removal ◽  
Helium Coolant ◽  
High Temperature Gas

Experimental Study on Oxidation of Graphite for HTR

2013 ◽  
Author(s):  
Yang Liu ◽  
Ximing Sun ◽  
Yujie Dong
Keyword(s):  
Electron Microscopy ◽  
High Temperature ◽  
Gas Flow ◽  
Normal Operation ◽  
Flow Rates ◽  
Water Ingress ◽  
Oxidized Graphite ◽  
Helium Coolant ◽  
Scanning Electron ◽  
High Temperature Gas

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.

Parametric Investigation of Brayton Cycle for High Temperature Gas-Cooled Reactors

Volume 4 ◽  
2004 ◽  
Author(s):  
Chang H. Oh ◽  
Richard L. Moore
Keyword(s):  
Carbon Dioxide ◽  
High Temperature ◽  
Supercritical Carbon Dioxide ◽  
Working Fluid ◽  
Brayton Cycle ◽  
Pebble Bed ◽  
Engineering Research ◽  
Cycle Efficiency ◽  
High Temperature Gas ◽  
Supercritical Carbon

The Idaho National Engineering and Environmental Laboratory (INEEL) has investigated a Brayton cycle efficiency improvement on a high temperature gas-cooled reactor (HTGR) as part of Generation-IV nuclear engineering research initiative. In this study, we are investigating helium Brayton cycles for the secondary side of an indirect energy conversion system. Ultimately we will investigate the improvement of the Brayton cycle using other fluids, such as supercritical carbon dioxide. Prior to the cycle improvement study, we established a number of baseline cases for the helium indirect Brayton cycle. The baseline cases are based on a 250 MW thermal pebble bed HTGR. In this study, we used the HYSYS computer code for optimization of the helium Brayton cycle and the balance of plant (BOP). In addition to the HYSYS process optimization, we performed parametric study to see the effect of important parameters on the cycle efficiency. For these parametric calculations, we also used a cycle efficiency model that was developed using the Visual Basic computer language. The results from this study are applicable to other reactor concepts such as a very high temperature gas-cooled reactor (VHTR), fast gas-cooled reactor (FGR), supercritical water reactor (SWR), and others. As part of this study we are currently investigated single-shaft vs. multiple shaft arrangement for cycle efficiency and comparison, which will be published in the next paper. The ultimate goal of this study is to use supercritical carbon dioxide for the HTGR power conversion loop in order to improve the cycle efficiency to values great than that of the helium Brayton cycle. This paper includes preliminary calculations of the steady state overall Brayton cycle efficiency based on the pebble bed reactor reference design (helium used as the working fluid) and compares those results with an initial calculation of a CO2 Brayton cycle.

Influence of the Graphite’s Lifespan on the Design Value of Fuel Burnup in High Temperature Gas-Cooled Reactors

2015 ◽  
Vol 1084 ◽  
pp. 313-316
Author(s):  
Denis F. Baybakov ◽  
Aleksey V. Golovatsky ◽  
Artem G. Naymushin ◽  
Vladimir N. Nesterov ◽  
Savva N. Savanyuk ◽  
...  
Keyword(s):  
High Temperature ◽  
Nuclear Fuel ◽  
Reactor Core ◽  
Fuel Burnup ◽  
Axial Distribution ◽  
Design Value ◽  
Helium Coolant ◽  
High Temperature Gas

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.

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