2014
DOI: 10.1016/j.jnucmat.2013.11.032
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Oxidation rate of nuclear-grade graphite IG-110 in the kinetic regime for VHTR air ingress accident scenarios

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Cited by 41 publications
(18 citation statements)
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“…Table 1 compares the results obtained by the method recommended by ASTM D7542 and the proposed method. The obtained activation energy of graphite IG-110 (220 kJ/mol) based on the proposed method is closer to those of other studies (218 kJ/mol 12 and 222 kJ/mol 19 ) with sufficient O 2 supply comparing with 201 kJ/mol 21 and 205 kJ/mol 32 based on experiment conditions recommended by ASTM D7542 standard. In addition, the standard errors of the proposed method are smaller.…”
Section: Resultssupporting
confidence: 82%
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“…Table 1 compares the results obtained by the method recommended by ASTM D7542 and the proposed method. The obtained activation energy of graphite IG-110 (220 kJ/mol) based on the proposed method is closer to those of other studies (218 kJ/mol 12 and 222 kJ/mol 19 ) with sufficient O 2 supply comparing with 201 kJ/mol 21 and 205 kJ/mol 32 based on experiment conditions recommended by ASTM D7542 standard. In addition, the standard errors of the proposed method are smaller.…”
Section: Resultssupporting
confidence: 82%
“…For the high gas flow rate (10 L/min), we got the related data including surface areas from previous study 32 . The calculation result of activation energy of graphite IG-110, 220 kJ/mol, echoed the results of previous studies with more adequate O 2 supply, 218 kJ/mol 12 and 222 kJ/mol 19 , compared with 201 kJ/mol 21 or 205 kJ/mol 32 under the experiment condition recommended by ASTM D7542. For the low gas flow rate (0.2 L/min), nuclear graphite ET-10, produced by IBIDEN Co. Ltd, was oxidized by a 0.2 L/min mixture gas (helium and O 2 , 10% or 20% O 2 mole fraction) at 650–850 °C.…”
Section: Introductionsupporting
confidence: 82%
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“…Schematic diagram of the nuclear steam supply system [22] Such pressure vessel configuration is intended to reduce the possibility of water intrusion into the reactor. The intrusion of water and also air from the steam generator into the reactor core can cause corrosion in the reactor structure which consists mainly of graphite [23,24]. The blower or compressor used to circulate helium gas in the primary cooling system loop is installed at the top of the pressure vessel for the steam generator.…”
Section: Nuclear Steam Supply Systemmentioning
confidence: 99%