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Articles

Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurized water reactor primary coolant under irradiation (1) evaluation of water radiolysis

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Pages 448-458 | Received 23 Jan 2023, Accepted 18 Jul 2023, Published online: 31 Jul 2023

References

  • Uchida S, Katsumura Y. Water chemistry technology – one of the key technologies for safe and reliable nuclear power plant operation. J Nucl Sci Technol. 2013;50(4):346–362. doi: 10.1080/00223131.2013.773171
  • Cowan RL Mitigation of IGSCC of BWR internals with hydrogen water chemistry. Proceedings of the International Conference on Water Chemistry Nuclear Reactor Systems, Water Chemistry 7; 1996 Oct 13–17; Bournemouth. British Nuclear Energy Society; 1996. p. 196–206.
  • Scott PM. 2000 F.N. Speller award lecture: stress corrosion cracking in pressurized water reactors— Interpretation, modelling, and remedies. Corrosion. 2000;56(8):771–782. doi: 10.5006/1.3280580
  • Haas C, Ahluwalia K, Kucuk A, et al. PWR operation with elevated hydrogen. Proceedings of International Conference on Water Chemistry of Nuclear Reactor Systems, NPC2008; 2008 Sep 15–18; Berlin, Germany: VGB Power Tech [CD-ROM]; 2008.
  • Nordann F Worldwide chemistry objectives and solutions for NPP. Proceedings of International Conference on Water Chemistry of Nuclear Reactor Systems, NPC2008; 2008 Sep 15–18; Berlin, Germany : VGB Power Tech [CD-ROM]; 2008.
  • Takiguchi H, Ullberg M, Uchida S. Optimization of dissolved hydrogen concentration for control of primary coolant radiolysis in pressurized water reactors. J Nucl Sci Technol. 2004;41(5):601–609. doi: 10.1080/18811248.2004.9715523
  • Hanawa S, Satoh T, Mori Y, et al. A Water radiolysis code for the irradiation loop system. J Power Energy Syst. 2007;1(2):123–129. doi: 10.1299/jpes.1.123
  • Uchida S, Wada Y, Yamamoto S, et al. Verification and validation procedures of calculation codes for determining corrosive conditions in the BWR primary cooling system based on water radiolysis and mixed potential models. J Nucl Sci Technol. 2014;51(1):24–36. doi: 10.1080/00223131.2013.842945
  • Elliot A, Bartels DM. The Reaction set, rate constants and g-values for the simulation of radiolysis of light water over the range 20° to 350°C based on information available in 2008. Mississauga (Canada): Atomic Energy of Canada Limited; 2009. Report no.153-127160-450-001.
  • Uchida S, Naitoh M, Okada H, et al. Water chemistry guidance in nuclear power plants in Japan. Power Plant Chem. 2012;14(1):4–16.
  • Christensen H, Molander A, Lassing A, et al. Experimental studies of radiolysis in an in-core loop in the Studsvik R2 reactor. Proceedings of Water Chemistry of Nuclear Reactor Systems, Water Chemistry 7; 1996 Oct. 13–17: Bournemouth, UK, British Nuclear Energy Society (BNES). p.138–140.
  • Atomic Energy Society of Japan, Handbook of water chemistry of nuclear reactor system. 2nd ed Tokyo (Japan): Corona Publishing Co. Ltd; 2022. ISBN978-4-339-06662-3 C3043.
  • Cowan RL, Indig ME, Kass JN Experience with hydrogen water chemistry in boiling water reactors. Proceedings of the International Conference on Water Chemistry Nuclear Reactor Systems, Water Chemistry 4; 1986 Oct 13–17; Bournemouth, UK. British Nuclear Energy Society (BNES); 1986. p.29–36.
  • Hettiarachchi S, Law RJ, Miller WD et al. First application of NobleChemTM to an operating BWR. Proceedings of the 1998 JAIF Conference on Water Chemistry of Nuclear Reactor Systems; 1998 Oct. 13-16; Kashiwazaki, Japan: Japan Atomic Industrial Forum (JAIF). p.155.
  • Hettiarachchi S, Cowan RL, Law RJ et al. NobleChemTM technology for life extension of BWRs – Field experiences. Proceedings of the International Conference of Water Chemistry of Nuclear Power Systems 8; 2000, Oct. 22-26, Bournmouth, UK: British Nuclear Energy Society (BNES). P.116–121.
  • Wada Y, Uchida S, Nakamura M et al. Empirical understanding of the dependency on BWR designs for HWC effectiveness. J Nucl Sci Technol. 1999;36(2):169–178. doi: 10.1080/18811248.1999.9726195
  • Uchida S, Satoh T, Sugama J et al. Effects of hydrogen peroxide on corrosion of stainless steel (III) - evaluation of electric resistance of oxide film by equivalent circuit analysis for frequency dependent complex impedances. J Nucl Sci Technol. 2005;42(1):66–74. doi: 10.1080/18811248.2005.9726365
  • Ibe E, Nagase M, Sakagami M, et al. Radiolytic environments in boiling water reactor cores. J Nucl Sci Technol. 1987;24(3):220–226. doi: 10.1080/18811248.1987.9735796
  • Ichikawa N, Takagi J. Precise evaluation of corrosion environments of structural materials under complex water flow condition, (II). J Nucl Sci Technol. 2003;40(11):941–950. doi: 10.1080/18811248.2003.9715437
  • Yeh TK, McDonald DD. The efficiency of noble metals in reducing the corrosion potential in the primary coolant circuits of boiling water reactors operating under hydrogen water chemistry operation. Journal Of Nuclear Science And Technology. 2006;43(10):1228–1236. doi: 10.1080/18811248.2006.9711216
  • Ibe E, Karasawa H, Uchida S. Radiation chemistry of radioactive nitrogen species in BWR reactor cores. J Nucl Sci Technol. 1991;28(4):347–355. doi: 10.1080/18811248.1991.9731367
  • Pathania RS, McIlree R A review of the effect of hydrogen on stress corrosion cracking of alloy 600 in 360 C water. Proceedings of Third International Symposium On Environmental Degradation of Materials in Nuclear Power Systems – Water reactors; 1988 Aug 30-Sept 3; Warrendale, USA: The Minerals, Metals and Materials Society (TMS). p. 551–526.
  • Andresen P, Hickling J, Ahluwalia A et al. Effect of dissolved H2 in primary water on the SCC growth rate of Ni alloys. Proceedings of International Conference on Water Chemistry of Nuclear Reactor Systems, NPC2008; 2008 Sept 15-18; Berlin, Germany: VGB Power Tech [CD-ROM].
  • König M, Norring K, Gott K et al. The influence of hydrogen concentration on the PWSCC susceptibility in alloy 600 in simulated primary water at 300°C. Proceedings of International Symposium on Contribution of Materials Investigations and Operating Experience to LWRs’ Safety, Performance and Reliability, Fontevraud IV. 1998 Sep 14-18; Paris, France: Société française d’énergie nucléaire (SFEN). p. 13a-A703.
  • Molander A, Jenssen A, Norring K et al. Comparison of PWSCC initiation and crack growth data for Alloy 600. Proceedings of International Conference on Water Chemistry of Nuclear Reactor Systems, NPC2008; 2008 Sep 15–18; Berlin, Germany: VGB Power Tech [CD-ROM].
  • Uchida S, Naitoh M, Okada H et al. An empirical model for the corrosion of stainless steel in BWR primary coolant. Corros Eng Sci Technol. 2017;52(8):587–595. doi: 10.1080/1478422X.2017.1357960
  • Urquidi-Macdonald M, Pitt J, Macdonald DD. The impact of radiolytic yield on the calculated ECP in PWR primary coolant circuits. J Nucl Mat. 2007;362(1):1–13. doi: 10.1016/j.jnucmat.2006.10.012
  • Burns WG, Moor ME, Radiation enhancement of zircaloy corrosion in boiling water system: a study of simulated radiation chemical kinetics, Proceedings of First International Conference on Water Chemistry of Nuclear Reactor Systems, Water Chemistry 1. 1978 Oct 14-17; Bournemouth, UK. No. 31, 281, British Nuclear Energy Society.
  • Hata K, Hanawa S, Chimi Y et al. Optimization of dissolved hydrogen concentration for mitigating corrosive conditions of pressurised water reactor primary coolant under irradiation (2) evaluation of electrochemical corrosion potential. J Nucl Sci Technol. 2022;60(8):867–880. doi: 10.1080/00223131.2022.2127955
  • Division of Water Chemistry (DWC). Latest situation and major subjects on evaluation procedures of corrosive conditions in BWR primary coolant. 2022, DWC Report #2022-0001, Division of water chemistry, atomic energy society of Japan (in Japanese).
  • Muroya Y, Yamashita S, Lertnaisat P et al. Rate constant for the H˙ + H2O → OH + H2 reaction at elevated temperatures measured by pulse radiolysis. Phys Chem Chem Phys. 2017;19(45):30834–30841. doi: 10.1039/C7CP06010F

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