|
[1] J.Skea, Global warming: The Greenpeace report, Energy Policy. 20 (2003) 589–590. [2] V.Tulpulé, S.Brown, J.Lim, C.Polidano, H.Pant, B.Fisher, The Kyoto protocol: An economic analysis using GTEM, Energy J. 20 (1999) 257–285. [3] JAERI, Design of high temperature engineering test reactor (HTTR), (1994). [4] C.Contescu, S.Azad, D.Miller, M.Lance, F.Baker, T.Burchell, Practical aspects for characterizing air oxidation of graphite, J. Nucl. Mater. 381 (2008) 15–24. [5] C.Oh, H.No, Experimental Validation of Stratified Flow Phenomena, Graphite Oxidation, and Mitigation Strategies of Air Ingress Accidents PI, 1400 (2004). [6] E.Kim, H.No, B.Kim, C.Oh, Estimation of graphite density and mechanical strength variation of VHTR during air-ingress accident, Nucl. Eng. Des. 238 (2008) 837–847. [7] E.Kim, H.No, Experimental study on the oxidation of nuclear graphite and development of an oxidation model, J. Nucl. Mater. 349 (2006) 182–194. [8] C.Contescu, T.Guldan, P.Wang, T.Burchell, The effect of microstructure on air oxidation resistance of nuclear graphite, Carbon N. Y. 50 (2012) 3354–3366. [9] M.El-Genk, J.Tournier, Comparison of oxidation model predictions with gasification data of IG-110, IG-430 and NBG-25 nuclear graphite, J. Nucl. Mater. 420 (2012) 141–158. [10] S.Shiozawa, S.Fujikawa, T.Lyoku, K.Kunitomi, Y.Tachibana, Overview of HTTR design features, Nucl. Eng. Des. 233 (2004) 11–21. [11] DOE, Multi-Year Research, Development and Demonstration Plan, 2012. [12] E.Fermi, Elementary Theory of the Chain-reacting Pile, Science 105 (1947) 27–32. [13] P.Cameron, The background and status of the gas cooled reactor in the United Kingdom, Ann. Nucl. Energy. 5 (1978) 489–505. [14] M.Ogawa, T.Nishihara, Present status of energy in Japan and HTTR project, in: Nucl. Eng. Des. (2004) 5–10. [15] S.Shiozawa, S.Fujikawa, T.Lyoku, K.Kunitomi, Y.Tachibana, Overview of HTTR design features, Nucl. Eng. Des. 233 (2004) 11–21. [16] S.Penner, R.Seiser, K.R.Schultz, Steps toward passively safe, proliferation-resistant nuclear power, Prog. Energy Combust. Sci. 34 (2008) 275–287. [17] S.Shiozawa, S.Fujikawa, T.Lyoku, K.Kunitomi, Y.Tachibana, Overview of HTTR design features, in: Nucl. Eng. Des. (2004) 11–21. [18] T.Oku, M.Ishihara, Lifetime evaluation of graphite components for HTGRs, Nucl. Eng. Des. 227 (2004) 209–217. [19] T.Takeda, M.Hishida, Study on the passive safe technology for the prevention of air ingress during the primary-pipe rupture accident of HTGR, Nucl. Eng. Des. 200 (2000) 251–259. [20] T.Takeda, M.Hishida, Studies on molecular diffusion and natural convection in a multicomponent gas system, Int. J. Heat Mass Transf. 39 (1996) 527–536. [21] J.Lee, T.Ghosh, S.Loyalka, Oxidation rate of nuclear-grade graphite IG-110 in the kinetic regime for VHTR air ingress accident scenarios, J. Nucl. Mater. 446 (2014) 38–48. [22] K.Minato, T.Ogawa, Advanced concepts in triso fuel, in: Compr. Nucl. Mater., (2012) 215–236. [23] S.Ball, M.Richards, S.Shepelev, Sensitivity studies of air ingress accidents in modular HTGRs, Nucl. Eng. Des. 238 (2008) 2935–2942. [24] Y.Ferng, C.Chi, CFD investigating the air ingress accident for a HTGR simulation of graphite corrosion oxidation, Nucl. Eng. Des. 248 (2012) 55–65. [25] D.Chung, Review: Graphite, J. Mater. Sci. 37 (2002) 1475–1489. [26] H.Pierson, Handbook of carbon, graphite, diamond and fullerenes: Properties, Processing, and Applications, Noyes Publ. (1993) 1–399. [27] S.Schimmelpfennig, B.Glaser, One Step Forward toward Characterization: Some Important Material Properties to Distinguish Biochars, J. Environ. Qual. 41 (2012) 1001. [28] J.Fachinger, W.vonLensa, T.Podruhzina, Decontamination of nuclear graphite, Nucl. Eng. Des. 238 (2008) 3086–3091. [29] M.Stempniewicz, L.Winters, S.A.Caspersson, Analysis of dust and fission products in a pebble bed NGNP, in: Nucl. Eng. Des. 2012: pp. 433–442. [30] Z.Li, D.Chen, X.Fu, W.Miao, Z.Zhang, The influence of pores on irradiation property of selected nuclear graphites, Adv. Mater. Sci. Eng. 2012 (2012) 1–7. [31] G.Hall, B.Marsden, S.Fok, The microstructural modelling of nuclear grade graphite, J. Nucl. Mater. 353 (2006) 12–18. [32] Y.Shtrombakh, B.Gurovich, P.Platonov, V.Alekseev, Radiation damage of graphite and carbon-graphite materials, J. Nucl. Mater. 225 (1995) 273–301. [33] P.Fanning, M.Vannice, A DRIFTS study of the formation of surface groups on carbon by oxidation, Carbon N. Y. 31 (1993) 721–730. [34] J.Kane, C.Contescu, R.Smith, G.Strydom, W.Windes, Understanding the reaction of nuclear graphite with molecular oxygen: Kinetics, transport, and structural evolution, J. Nucl. Mater. 493 (2017) 343–367. [35] J.Bonal, A.Kohyama, J.Laan, L.Snead, Graphite, Ceramics, and Ceramic Composites for Nuclear Power Systems, MRS Bull. 34 (2009) 28–34. [36] J.Bulau, A Monitoring for Control of Carbon-Carbon Pyrolysis, Ultrason. Symp. (1988) 1057–1063. [37] R.Krishna, A.Jones, L.McDermott, B.Marsden, Neutron irradiation damage of nuclear graphite studied by high-resolution transmission electron microscopy and Raman spectroscopy, J. Nucl. Mater. 467 (2015) 557–565. [38] K.Wen, T.Marrow, B.Marsden, The microstructure of nuclear graphite binders, Carbon N. Y. 46 (2008) 62–71. [39] J.Okada, T.Ikegawa, Combustion rate of artificial graphites from 700°C to 2000°C in air [5], J. Appl. Phys. 24 (1953) 1249–1250. [40] E.Loren Fuller, J.M.Okoh, Kinetics and mechanisms of the reaction of air with nuclear grade graphites: IG-110, J. Nucl. Mater. 240 (1997) 241–250. [41] F.Emmerich, Evolution with heat treatment of crystallinity in carbons, Carbon N. Y. 33 (1995) 1709–1715. [42] P.Wang, C.Contescu, S.Yu, T.D.Burchell, Pore structure development in oxidized IG-110 nuclear graphite, J. Nucl. Mater. 430 (2012) 229–238. [43] S.Ahmed, M.Back, The role of the surface complex in the kinetics of the reaction of oxygen with carbon, Carbon N. Y. 23 (1985) 513–524. [44] M.El-Genk, J.Tournier, Development and validation of a model for the chemical kinetics of graphite oxidation, J. Nucl. Mater. 411 (2011) 193–207. [45] P.Walker, R.Taylor, J.Ranish, An update on the carbon-oxygen reaction, Carbon N. Y. 29 (1991) 411–421. [46] L.Radovic, H.Jiang, A.Lizzio, A Transient Kinetics Study of Char Gasification in Carbon Dioxide and Oxygen, Energy and Fuels. 5 (1991) 68–74. [47] Z.Pan, R.Yang, Strongly Bonded Oxygen in Graphite: Detection by High-Temperature TPD and Characterization, Ind. Eng. Chem. Res. 31 (1992) 2675–2680. [48] W.Jiang, G.Nadeau, K.Zaghib, K.Kinoshita, Thermal analysis of the oxidation of natural graphite - Effect of particle size, Thermochim. Acta. 351 (2000) 85–93. [49] G.Miessen, F.Behrendt, O.Deutschmann, J.Warnatz, Numerical studies of the heterogeneous combustion of char using detailed chemistry, Chemosphere. 42 (2001) 609–613. [50] J.Kane, C.Karthik, D.Butt, W.Windes, R.Ubic, Microstructural characterization and pore structure analysis of nuclear graphite, J. Nucl. Mater. 415 (2011) 189–197. [51] F.Kang, K.Shen, W.Shen, Z.Huang, Status of Isotropic Graphite Manufacture and Carbon Industry in China, (2014). [52] C.Contescu, Characterization of Porosity Development in Oxidized Graphite using Automated Image Analysis, 2009. [53] ASTM Standard D7542–15, Standard Test Method for Air Oxidation of Carbon and Graphite in the Kinetic Regime, ASTM International, West Conshohocken, PA, USA, 2015. [54] J.Lee, T.Ghosh, S.Loyalka, Oxidation rate of graphitic matrix material in the kinetic regime for VHTR air ingress accident scenarios, J. Nucl. Mater. 451 (2014) 48–54. [55] J.ONG, On the kinetics of oxidation of graphite, Carbon 2 (1964) 281–297. [56] E.Kim, K.Lee, H.No, Analysis of geometrical effects on graphite oxidation through measurement of internal surface area, J. Nucl. Mater. 348 (2006) 174–180. [57] M.Takahashi, M.Kotaka, H.Sekimoto, Burn-off and production of CO and CO2 in the oxidation of nuclear reactor- grade graphites in a flow system, J. Nucl. Sci. Technol. 31 (1994) 1275–1286. [58] Z.Hu, Z.Li, D.Chen, W.Miao, Z.Zhang, CO2 corrosion of IG-110 nuclear graphite studied by gas chromatography, J. Nucl. Sci. Technol. 51 (2014) 487–492. [59] D.Macdonald, M.Urquidi-Macdonald, J.Mahaffy, A.Jain, H.Kim, C.Gupta, J.Pitt, Electrochemistry of Water-Cooled Nuclear Reactors. NEER, PA, USA, 2006. [60] M.El-genk, J.Tournier, C.Contescu, Chemical kinetics parameters and model validation for the gasification of PCEA nuclear graphite, J. Nucl. Mater. 444 (2014) 112–128. [61] S.Chi, G.Kim, Comparison of the oxidation rate and degree of graphitization of selected IG and NBG nuclear graphite grades, J. Nucl. Mater. 381 (2008) 9–14. [62] X.Luo, J.Robin, S.Yu, Comparison of Oxidation Behaviors of Different Grades of Nuclear Graphite, Nucl. Sci. Eng. 151 (2005) 121–127. [63] J.Jo, T.K.Ghosh, S.K.Loyalka, Comparison of NBG-18 , NBG-17 , IG-110 and IG-11 oxidation kinetics in, J. Nucl. Mater. 500 (2018) 64–71. [64] W.Huang, S.Tsai, C.Yang, J.Kai, The relationship between microstructure and oxidation effects of selected IG- and NBG-grade nuclear graphites, J. Nucl. Mater. 454 (2014) 149–158. [65] W.Huang, S.Tsai, I.Chiu, C.Chen, J.Kai, The oxidation effects of nuclear graphite during air-ingress accidents in HTGR, Nucl. Eng. Des. 271 (2014) 270–274. [66] X.Sun, Y.Dong, Y.Zhou, Z.Li, L.Shi, Y.Sun, Z.Zhang, Effects of reaction temperature and inlet oxidizing gas flow rate on IG-110 graphite oxidation used in HTR-PM, J. Nucl. Sci. Technol. 54 (2017) 196–204. [67] X.Luo, S.Yu, X.Sheng, S.He, Temperature effect on IG-11 graphite wear performance, Nucl. Eng. Des. 235 (2005) 2261–2274. [68] J.Eapen, R.Krishna, T.Burchell, K.Murty, Early damage mechanisms in nuclear grade graphite under irradiation, Mater. Res. Lett. 2 (2014) 43–50. [69] T.Burchell, R.Bratton, W.Windes, NGNP Graphite Selection and Acquisition Strategy, 2007. [70] B.J.Marsden, G.N.Hall, Graphite in gas-cooled reactors, Elsevier Inc., 2012. [71] J.Sumita, T.Shibata, I.Fujita, E.Kunimoto, M.Yamaji, M.Eto, T.Konishi, K.Sawa, Development of evaluation method with X-ray tomography for material property of IG-430 graphite for VHTR/HTGR, Nucl. Eng. Des. 271 (2014) 314–317. [72] A.Campbell, Y.Katoh, M.Snead, K.Takizawa, Property changes of G347A graphite due to neutron irradiation, Carbon N. Y. 109 (2016) 860–873. [73] G.Haag, Properties of ATR-2E Graphite and Property Changes due to Fast Neutron Irradiation (Jülich-4183), Jülich-4183. 4183 (2005) 177. [74] C.Oh, H.No, Experimental Validation of Stratified Flow Phenomena, Graphite Oxidation, and Mitigation Strategies of Air Ingress Accidents PI, 1400 (2004). [75] ASTM Standard C559-90, Standard Test Method for Bulk Density by Physical Measurements of Manufactured Carbon and Graphite Articles, ASTM International, West Conshohocken, PA, USA, 2000. [76] 材料電子顯微鏡學 ,國科會精儀中心叢書 ,科儀叢書 3, n.d. [77] P.Webb, Micromeritics, Data Collect. Reduct. Present. An Int. Sales Support Doc. (1993). [78] P.Webb, An Introduction To The Physical Characterization of Materials by Mercury Intrusion Porosimetry with Emphasis On Reduction And Presentation of Experimental Data, Micrometrics Instrum. Corp. (2001) 23. [79] D.Baker, J.Morris, Structural damage in graphite occurring during pore size measurements by high pressure mercury, Carbon N. Y. 9 (1971) 687–690. [80] K.Mergia, K.Stefanopoulos, N.Ordás, C.García-Rosales, A comparative study of the porosity of doped graphites by small angle neutron scattering, nitrogen adsorption and helium pycnometry, Microporous Mesoporous Mater. 134 (2010) 141–149. [81] M.Seeh, A.Pavlovic, X-ray diffraction, thermal expansion, electrical conductivity, and optical microscopy studies of coal based graphites, Carbon N. Y. 31 (1993) 557–564. [82] S.Seo, J.Roh, S.Kim, S.Chi, E.Kim, Thermal Emissivity of Nuclear Graphite as a Function of its Oxidation Degree (1): Effects of Density, Porosity, and Microstructure, Carbon Lett. 12 (2011) 8–15. [83] D.Yang, A.Velamakanni, G.Bozoklu, S.Park, M.Stoller, R.Piner, S.Stankovich, Chemical analysis of graphene oxide films after heat and chemical treatments by X-ray photoelectron and Micro-Raman spectroscopy, Carbon 47 (2009) 145–152. [84] M.Pimenta, G.Dresselhaus, M.Dresselhaus, L.Cançado, A.Jorio, R.Saito, Studying disorder in graphite-based systems by Raman spectroscopy, Phys. Chem. Chem. Phys. 9 (2007) 1276–1291. [85] F.Tuinstra, J.Koenig, Raman Spectrum of Graphite, J. Chem. Phys. 53 (1970) 1126–1130. [86] Y.Yamada, H.Yasuda, K.Murota, M.Nakamura, T.Sodesawa, S.Sato, Analysis of heat-treated graphite oxide by X-ray photoelectron spectroscopy, J. Mater. Sci. 48 (2013) 8171–8198. [87] C.Tang, Y.Kwon, J.Leckie, Effect of membrane chemistry and coating layer on physiochemical properties of thin film composite polyamide RO and NF membranes. I. FTIR and XPS characterization of polyamide and coating layer chemistry, Desalination. 242 (2009) 149–167. [88] B.Kartick, S.Srivastava, I.Srivastava, Green synthesis of graphene., J. Nano sci. 13 (2013) 4320–4. [89] J.Chalmers, N.Everall, S.Ellison, Specular reflectance: A convenient tool for polymer characterisation by FTIR-microscopy, Micron. 27 (1996) 315–328. [90] IR / FTIR 樣品處理及測定 IR / FTIR 樣品處理及測定, National Tsing Hua University (2016) 1–11. [91] S.Chi, G.Kim, Effects of air flow rate on the oxidation of NBG-18 and NBG-25 nuclear graphite, J. Nucl. Mater. 491 (2017) 37–42. [92] X.Luo, R.Jean-Charles, Y.Suyuan, Theoretical analysis of mass transfer and reaction in a porous medium applied to the gasification of graphite by water vapor, Nucl. Eng. Des. 236 (2006) 938–947. [93] J.Lee, T.Ghosh, S.Loyalka, Oxidation rate of nuclear-grade graphite IG-110 in the kinetic regime for VHTR air ingress accident scenarios, J. Nucl. Mater. 446 (2014) 38–48. [94] A.Theodosiou, A.Jones, B.Marsden, Thermal oxidation of nuclear graphite: A large scale waste treatment option, PLoS One. 12 (2017) [95] E.Kim, H.No, Experimental study on the oxidation of nuclear graphite and development of an oxidation model, J. Nucl. Mater. 349 (2006) 182–194. [96] R.Moormann, H.Hinssen, K.Kühn, Oxidation behaviour of an HTR fuel element matrix graphite in oxygen compared to a standard nuclear graphite, Nucl. Eng. Des. 227 (2004) 281–284. [97] P.Campbell, R.Mitchell, The impact of the distributions of surface oxides and their migration on characterization of the heterogeneous carbon-oxygen reaction, Combust. Flame. 154 (2008) 47–66. [98] K.Jones, G.Laudone, G.Matthews, A multi-technique experimental and modelling study of the porous structure of IG-110 and IG-430 nuclear graphite, Carbon N. Y. 128 (2018) 1–11. [99] J.Dickinson, J.Shore, Observations concerning the determination of porosities in graphites, Carbon N. Y. 6 (1968) 937–941. [100] H.Hinssen, K.Kühn, R.Moormann, B.Schlögl, M.Fechter, M.Mitchell, Oxidation experiments and theoretical examinations on graphite materials relevant for the PBMR, Nucl. Eng. Des. 238 (2008) 3018–3025. [101] R.Moormann, H.K.Hinssen, K.Kühn, Oxidation behaviour of an HTR fuel element matrix graphite in oxygen compared to a standard nuclear graphite, Nucl. Eng. Des. 227 (2004) 281–284. [102] R.Ubic, D.Butt, W.Windes, Irradiation Creep in Graphite, United States, 2014. [103] P.Thrower, J.Bognet, G.Mathew, The influence of oxidation on the structure and strength of graphite-I. Materials of different structure, Carbon. 20 (1982) 457–464. [104] A.Ferrari, Raman spectroscopy of graphene and graphite: Disorder, electron-phonon coupling, doping and nonadiabatic effects, Solid State Commun. 143 (2007) 47–57. [105] R.Krishna, A.Jones, R.Edge, B.Marsden, Residual stress measurements in polycrystalline graphite with micro-Raman spectroscopy, Radiat. Phys. Chem. 111 (2015) 14–23. [106] B.März, K.Jolley, R.Smith, H.Wu, Near-surface structure and residual stress in as-machined synthetic graphite, Mater. Des. 159 (2018) 1–27. [107] R.Krishna, J.Wade, A.Jones, M.Lasithiotakis, P.Mummery, B.Marsden, An understanding of lattice strain, defects and disorder in nuclear graphite, Carbon 124 (2017) 314–333. [108] H.Freeman, A.Jones, M.Ward, F.Hage, N.Tzelepi, Q.Ramasse, A.Scott, R.M.D.Brydson, On the nature of cracks and voids in nuclear graphite, Carbon 103 (2016) 45–55. [109] O.Frank, G.Tsoukleri, I.Riaz, K.Papagelis, J.Parthenios, A.C.Ferrari, A.K.Geim, K.S.Novoselov, C.Galiotis, Development of a universal stress sensor for graphene and carbon fibres, Nat. Commun. 2 (2011). [110] B.März, K.Jolley, T.Marrow, Z.Zhou, M.Heggie, R.Smith, H.Wu, Data related to the mesoscopic structure of iso-graphite for nuclear applications, Data Br. 19 (2018) 651–659. [111] R.VanGrieken, A.Markowicz, Handbook of X-ray spectrometry. Second edition, 2002. [112] G.Kothleitner, Fundamentals of electron energy-loss spectroscopy, IOP Conf. Ser. Mater. Sci. Eng. 109 (2016) 12007. [113] E.Heintz, W.Parker, Catalytic effect of major impurities on graphite oxidation, Carbon N. Y. 4 (1966) 473–482. [114] D.McKee, Metal oxides as catalysts for the oxidation of graphite, Carbon 8 (1970) 623–635. [115] J.Han, K.Cho, K.Lee, H.Kim, Porous graphite matrix for chemical heat pumps, Carbon 36 (1998) 1801–1810. [116] A.Baranov, A.Bekhterev, Y.Bobovich, V.Petrov, Interpretation of certain characteristics in Raman spectra of graphite and glassy carbon, Opt. Spektrosk. 62 (1987) 1036. [117] C.Thomsen, S.Reich, Double resonant raman scattering in graphite, Phys. Rev. Lett. 85 (2000) 5214–5217. [118] A.Eckmann, A.Felten, A.Mishchenko, L.Britnell, R.Krupke, K.S.Novoselov, C.Casiraghi, Probing the nature of defects in graphene by Raman spectroscopy, Nano Lett. 12 (2012) 3925–3930. [119] D.Carlson, S.Ball, Perspectives on understanding and verifying the safety terrain of modular high temperature gas-cooled reactors, Nucl. Eng. Des. 306 (2016) 117–123. [120] E.Kim, H.No, B.Kim, C.Oh, Estimation of graphite density and mechanical strength variation of VHTR during air-ingress accident, Nucl. Eng. Des. 238 (2008) 837–847. [121] H.No, H.Lim, J.Kim, C.Oh, L.Siefken, C.Davis, Multi-component diffusion analysis and assessment of GAMMA code and improved RELAP5 code, Nucl. Eng. Des. 237 (2007) 997–1008. [122] C.Oh, E.Kim, R.Schultz, M.Patterson, D.Petti, H.Kang, Comprehensive thermal hydraulics research of the very high temperature gas cooled reactor, in: Nucl. Eng. Des., (2010) 3361–3371. [123] C.Oh, E.Kim, Conceptual study on air ingress mitigation for VHTRs, Nucl. Eng. Des. 250 (2012) 448–464. [124] M.Davies, M.Bradford, A revised description of graphite irradiation induced creep, J. Nucl. Mater. 381 (2008) 39–45. [125] T.Burchell, K.Murty, J.Eapen, Irradiation induced creep of graphite, JOM. 62 (2010) 93–99.
|