Study of oxygen and steam interactions with rgt graphite
Keywords:
RGT graphite, oxidation, steam, oxygenAbstract
Corrosion in air and water remains a problem for graphite as an important structural material of nuclear reactors. Changes in the gas composition in corrosion chamber with samples of RGT graphite have been studied. The sample was linearly heated to 1100C with 10C /min rate, and held at this temperature for 1800 s. Then the sample was cooled down within the same rate. During the experiment changes in the gas composition in the chamber were registered within the mass range 1-70. The time and temperature dependencies of steam, oxygen and gaseous corrosion products of RGT graphite have been obtained. Arrhenius dependencies and activation energy of rate constants of graphite interaction with the following products were derived: oxygen-graphite (mole/(sm2Pa)),water-graphite (mole/(sm2Pa).References
[1] 1 Beskorovajnyj N.M., Kalin B.A., Platonov P.A., Chernov I.I. Konstrukcionnye materialy jadernyh reaktorov. – M.: Jenergoatomizdat, 1995. – 704 s.
[2] 2 Ohashi H., Sato H., Tachibana Y., Kunitomi K., Ogawa M. Concept of an Inherently-safe High Temperature Gas-cooled Reactor // AIP Conf. Proc. ICANSE2011. – 2012. – Vol. 1448. – P. 50-58.
[3] 3 Bundy F.P. Direct conversion of graphite to diamond is static pressure apparatus // J. Chem. Phys. – 1963. – Vol. 38. – P. 618-631.
[4] 4 Minato K., Fukuda K. Thermodynamic Analysis of Behavior of HTGR Fuel and Fission Products under Accidental Air or Water Ingress Conditions // Proc. IAEA Technical Committee Mtg. on Response of Fuel, Fuel Elements and Gas-cooled Reactor Cores under Accidental Air or Water Ingress Conditions, IAEA-TECDOC-784. – 1995. – P. 86-91.
[5] 5 El-Genk M. S., Tournier J.-M., Travis В. Graphite Oxidation Simulation in HTR Accident Conditions / 3 rd Year and Final Technical Report. – Institute for Space and Nuclear Power Studies, MSC01 1120, Project No. 09-830 to University of New Mexico, 2012.
[6] 6 Kabakchi S. A., Bulgakova G. P. Radiacionnaja himija v jadernom toplivnom cikle: uchebnoe posobie. – M.: Izd. centr RHTU im. D. I. Mendeleeva, 1997. – 96 s.
[2] 2 Ohashi H., Sato H., Tachibana Y., Kunitomi K., Ogawa M. Concept of an Inherently-safe High Temperature Gas-cooled Reactor // AIP Conf. Proc. ICANSE2011. – 2012. – Vol. 1448. – P. 50-58.
[3] 3 Bundy F.P. Direct conversion of graphite to diamond is static pressure apparatus // J. Chem. Phys. – 1963. – Vol. 38. – P. 618-631.
[4] 4 Minato K., Fukuda K. Thermodynamic Analysis of Behavior of HTGR Fuel and Fission Products under Accidental Air or Water Ingress Conditions // Proc. IAEA Technical Committee Mtg. on Response of Fuel, Fuel Elements and Gas-cooled Reactor Cores under Accidental Air or Water Ingress Conditions, IAEA-TECDOC-784. – 1995. – P. 86-91.
[5] 5 El-Genk M. S., Tournier J.-M., Travis В. Graphite Oxidation Simulation in HTR Accident Conditions / 3 rd Year and Final Technical Report. – Institute for Space and Nuclear Power Studies, MSC01 1120, Project No. 09-830 to University of New Mexico, 2012.
[6] 6 Kabakchi S. A., Bulgakova G. P. Radiacionnaja himija v jadernom toplivnom cikle: uchebnoe posobie. – M.: Izd. centr RHTU im. D. I. Mendeleeva, 1997. – 96 s.
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Published
2015-07-13
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Thermal Physics and Related Techology
