Abstract
Predicting the electrical corrosion potential (ECP) of type 304 stainless steel, the structural material of recirculation pipes in fusion power plants, is important because the growth rate of intergranular stress corrosion crack (IGSCC) of 304 stainless steel is closely related to ECP. In this work, a new model has been developed, by modifying existing models, to calculate the ECP of recirculation pipes in future fusion power plant. The calculation results indicate that merely injecting hydrogen cannot reduce ECP below EIGSCC if the dose rate exceeds a threshold, other assisted water chemistry controlling method is necessary.
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Kwon J, Motta AT (2001) Radiation hardening in BWR core shrouds: relative roles of neutron and gamma irradiation. React Dosim Radiat Metrol Assess 1398:607–616
Kwon J, Motta AT (1999) Effect of radiation damage on BWR core-shroud cracking. Microstruct Process Irradiat Mater 540:483–488
Anderson DS (1985) Bwr hydrogen addition for Igscc. Trans Am Nucl Soc 49:49
Gordon GM, Horn RM, Otoole CS (1984) Implementation status of Igscc mitigation in domestic Bwr piping. Trans Am Nucl Soc 46:38–39
Gerber TL, Riccardella PC, Giannuzzi AJ (1984) Use of an Igscc damage index for cost-benefit evaluation of Bwr pipe cracking remedies. Mech Eng 106(8):87
Self JW (1985) Bwr recirculation piping inspection techniques for Igscc. Trans Am Nucl Soc 49:48
Stjarnsater J, Bengtsson B, Forssgren B et al (2011) The effect of grain size on Igscc in Ss 316 l in simulated Bwr environment. In: 15th International conference on environmental degradation of materials in nuclear power systems-water reactors, pp 505–517
Roychowdhury S, Kain V, Gupta M et al (2011) IGSCC crack growth in simulated BWR environment—effect of nitrogen content in non-sensitised and warm rolled austenitic stainless steel. Corros Sci 53(3):1120–1129
Zhou ZF, Chalkova E, Lvov SN et al (2007) Development of a hydrothermal deposition process for applying zirconia coatings on BWR materials for IGSCC mitigation. Corros Sci 49(2):830–843
Cowan RL (1997) The mitigation of IGSCC of BWR internals with hydrogen water chemistry. Nucl Energ J Br Nucl 36(4):257–264
Cowan RL, Gordon GM (1995) The mitigation of IGSCC susceptibility of BWR reactor internals. In: Annual meeting on nuclear technology ‘95, Proceedings, pp 383–384
Irving B (1991) Bwr plants cure Igscc with new technologies. Weld J 70(6):47–50
Molander A, Bengtsson B, Jansson C et al (1997) Influence of flow-rate on the critical potential for IGSCC of stainless steel in simulated BWR environment—a SSRT study. In: Proceedings of the eighth international symposium on environmental degradation of materials in nuclear power systems—water reactors, vols 1 and 2, pp 615–621
Macdonald D, Cragnolino G (1985) The critical potential for the IGSCC of sensitized type 304 SS in high temperature aqueous systems. In: Proceedings of the Proceedings of the 2nd international symposium environmental degradation of materials in nuclear power systems, Monterey, California
Indig ME, McIlree AR (1979) High-temperature electrochemical studies of the stress-corrosion of type-304 stainless-steel. Corrosion 35(7):288–295
Lee JB (1978) Electrochemical approach to corrosion problems of several iron–nickel–chromium alloys in high temperature, high pressure water. Ohio State University
Macdonald DD (1992) Viability of hydrogen water chemistry for protecting in-vessel components of boiling water-reactors. Corrosion 48(3):194–205
Yeh TK, Chu F (2000) Electrochemical corrosion potential modeling in the primary heat transport circuit of the Chinshan boiling water reactor under the condition of hydrogen water chemistry with noble metal coating. J Nucl Sci Technol 37(12):1063–1074
Yeh TK, Macdonald DD (1996) Modeling water chemistry, electrochemical corrosion potential, and crack growth rate in the boiling water reactor heat transport circuits. 3. Effect of reactor power level. Nucl Sci Eng 123(2):305–316
Yeh TK, Macdonald DD (1996) Modeling water chemistry, electrochemical corrosion potential, and crack growth rate in the boiling water reactor heat transport circuits. 2. Simulation of operating reactors. Nucl Sci Eng 123(2):295–304
Yeh TK, Macdonald DD, Motta AT (1995) Modeling water chemistry, electrochemical corrosion potential, and crack-growth rate in the boiling water-reactor heat-transport circuits. 1. The damage-predictor algorithm. Nucl Sci Eng 121(3):468–482
Lin CC, Kim YJ, Niedrach LW et al (1996) Electrochemical corrosion potential models for boiling-water reactor applications. Corrosion 52(8):618–625
Hirayama S, Kawabe T (1995) Roles of plasma neutron source reactor in development of fusion reactor engineering: comparison with fission reactor engineering. J Fusion Energ 14(4):343–352
Hickel B, Arvis M, Bjergbakke E et al (1993) Water radiolysis in fusion controlled reactors. J Chim Phys Pcb 90(4):755–765
Molander A (2006) Corrosion and water chemistry aspects concerning the tokamak cooling water systems of ITER. EFDA WP2005, Studsvik Nuclear AB, Sweden
Karditsas PJ (2011) Water radiolysis in fusion neutron environments. Fusion Eng Des 86(9–11):2701–2704
Fang Z, Cao XW, Tong LL et al (2018) An improved method for modelling coolant radiolysis in ITER. Fusion Eng Des 127:91–98
SAJI G (2012) Scientific bases of corrosion control for water-cooled fusion reactors such as iter. In: Proceedings of the 20th international conference on nuclear engineering and the Asme 2012 power conference—2012, vol 5, pp 29–39
Selman JR, Tobias CW (1975) Unsteady-state effects in limiting current measurements. J Electroanal Chem 65(1):67–85
Selman JR, Tobias CW (1972) Unsteady-state limiting currents at a rotating disk electrode. J Electrochem Soc 119(3):C112000
Han P, Bartels DM (1996) Temperature dependence of oxygen diffusion in H2O and D2O. J Phys Chem Us 100(13):5597–5602
Harvey AH, Span R, Fujii K et al (2009) Density of water: roles of the CIPM and IAPWS standards. Metrologia 46(3):196–198
Alvarez M, Barbato S (2006) Calculation of the thermodynamic properties of water using the IAPWS model. J Chil Chem Soc 51(2):891–900
Macdonald DD, Urquidimacdonald M (1991) A coupled environment model for stress-corrosion cracking in sensitized type-304 stainless-steel in Lwr environments. Corros Sci 32(1):51–81
Macdonald DD, Mankowski J, Karaminezhaadranjbar M et al (1988) Apparatus for controlled hydrodynamic electrochemical and corrosion studies in high-temperature aqueous systems. Corrosion 44(3):186–192
Tachibana M, Ishida K, Wada Y et al (2012) Determining factors for anodic polarization curves of typical structural materials of boiling water reactors in high temperature—high purity water. J Nucl Sci Technol 49(1–2):253–262
Nichols D, Hirt CW (1978) Numerical-simulation of Bwr vent clearing hydrodynamics. Trans Am Nucl Soc 28:416–417
Molander A (2008) A review of corrosion and water chemistry aspects concerning the tokamak cooling water systems of iter. The 2008 Annual Meeting
Gulden W, Ciattaglia S, Massaut V et al (2007) Main safety issues at the transition from ITER to fusion power plants. Nucl Fusion 47(7):S415–S421
Iida H, Khripunov V, Petrizzi L, Federici G (2004) ITER nuclear analysis report[J]. ITER report G, p 73
Ishidai K, Wada Y, Tachibana M et al (2007) Hydrogen and hydrazine co-injection to mitigate stress corrosion cracking of structural materials in boiling water reactors, (VI) the effect of ammonia on intergranular stress corrosion cracking. J Nucl Sci Technol 44(12):1550–1556
Wada Y, Ishida K, Tachibana M et al (2007) Hydrazine and hydrogen co-injection to mitigate stress corrosion cracking of structural materials in boiling water reactors (IV)—reaction mechanism and plant feasibility analysis. J Nucl Sci Technol 44(4):607–622
Ishida K, Wada Y, Tachibana M et al (2007) Hydrazine and hydrogen co-injection to mitigate stress corrosion cracking of structural materials in boiling water reactors (V) effects of hydrazine and dissolved oxygen on flow accelerated corrosion of carbon steel. J Nucl Sci Technol 44(2):222–232
Karasawa H, Ishida K, Wada Y et al (2006) Hydrazine and hydrogen co-injection to mitigate stress corrosion cracking of structural materials in boiling water reactors, (III) effects of adding hydrazine on Zircaloy-2 corrosion. J Nucl Sci Technol 43(10):1218–1223
Ishida K, Wada Y, Tachibana M et al (2006) Hydrazine and hydrogen co-injection to mitigate stress corrosion cracking of structural materials in boiling water reactors, (II)—reactivity of hydrazine with oxidant in high temperature water under gamma-irradiation. J Nucl Sci Technol 43(3):242–254
Ishida K, Wada Y, Tachibana M et al (2006) Hydrazine and hydrogen co-injection to mitigate stress corrosion cracking of structural materials in boiling water reactors, (I) temperature dependence of hydrazine reactions. J Nucl Sci Technol 43(1):65–76
Arkhipov OP, Bugaenko VL, Kabakchi SA et al (1997) Thermal and radiation characteristics of hydrazine in the primary loop of nuclear power plants with water-cooled, water-moderated reactors. Atom Energy 82(2):92–98
Kim YJ, Niedrach LW, Indig ME et al (1992) The application of noble-metals in light-water reactors. J Miner Met Mater Soc 44(4):14–18
Lin CC (2000) Hydrogen water chemistry technology in boiling water reactors. Nucl Technol 130(1):59–70
Wada Y, Uchida S, Nakamura M et al (1999) Empirical understanding of the dependency of hydrogen water chemistry effectiveness on BWR designs. J Nucl Sci Technol 36(2):169–178
Molander A, Pein K, Forsgren AL et al (1999) Corrosion potential monitoring in Swedish BWRs on hydrogen water chemistry. In: Proceedings of the ninth international symposium on environmental degradation of materials in nuclear power systems-water reactors, pp 453–459
Lertnaisat P, Katsumura Y, Mukai S et al (2014) Simulation of the inhibition of water alpha-radiolysis via H-2 addition. J Nucl Sci Technol 51(9):1087–1095
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This research is funded by National Natural Science Foundation of China (11775214), National Magnetic Confinement Fusion Science Program of China (2014GB122001).
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Fang, Z., Tang, J., Xiao, J. et al. Modelling electrical corrosion potential of 304 stainless steel under fusion power plant environment. J Radioanal Nucl Chem 319, 303–314 (2019). https://doi.org/10.1007/s10967-018-6299-x
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DOI: https://doi.org/10.1007/s10967-018-6299-x