Determining water chemistry conditions in nuclear reactor coolants

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;50:346–362.
   Web of Science ®Google Scholar
• Uchida S, Takiguchi H, Lister DH. Instrumentation for monitoring and control of water chemistry for light-water-cooled nuclear power plants. Power Plant Chem. 2010;12:278–295.
   Google Scholar
• Uchida S, Naitoh M, Okada H, Suzuku H. Water chemistry guidance in nuclear power plants in Japan. Power Plant Chem. 2012;14:278–295.
   Google Scholar
• Uchida S, Ishigure K, Takamatsu H, Takiguchi H, Nakagami M, Matsui M. Water chemistry data acquisition, processing, evaluation and diagnosis systems for nuclear power reactors. Paper presented at: 14th International Conference on the Properties of Water and Steam; 2004 Aug 31 to Sep 3; Kyoto: International Association for Properties of Water and Steam; p. 551–558.
   Google Scholar
• Yamashiro N, Uchida S, Satoh Y, Morishima Y, Yokoyama H, Satoh T, Sugama J, Yamada R. Determination of hydrogen peroxide in water by chemiluminescence detection, (i) Flow injection type hydrogen peroxide detection system. J Nucl Sci Technol. 2004;41:890–897.
   Web of Science ®Google Scholar
• Standards Committee. Chemical analysis for primary coolant of PWR – boron. AESJ-SC-S002:2010. Atomic Energy Society of Japan, Tokyo; 2010, in Japanese.
   Google Scholar
• Gjerde DT, Fritz JS. Ion chromatography. Weinheim: Wiley-VC; 2000.
   Google Scholar
• Welz B, Sperling M. Atomic absorption spectrometry. Weinheim: Wiley-VC; 1999.
   Google Scholar
• Vajda N, Larosa J, Pintér T, Keömley G, Bódizs D, Molnár, Zs. Analysis of actinides in the primary coolant of a WWER-440 type reactor. J Radioanal Nucl Chem. 2005;170(2):399–409.
   Web of Science ®Google Scholar
• Bolz M, Hoffman W, Ruehle W, Becker F. Characterization of colloids in primary coolant. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems 7; 1996 Oct 13–17; Bournemouth: British Nuclear Energy Society.
   Google Scholar
• Knoll GF. Radiation detection and measurement. 3rd ed. Weinheim: Wiley; 1999.
   Google Scholar
• Uchida S. Corrosion monitoring applications in nuclear power plants. In: Ritter S, Molander A, editors. Corrosion monitoring in nuclear systems. European Federation of Corrosion Publications, Number 56. Maney Publishing; 2010. ISBN-13: 978-1-906540-98-2.
   Google Scholar
• Nakayama N, Uchida S. Pressure balanced type membrane covered polarographic oxygen detectors for use in high temperature high pressure water; (ii) - Effects of environmental factors on detector performance in water at 285 °C. J Nucl Sci Technol. 1984;21:476–483.
   Web of Science ®Google Scholar
• IAEA. High temperature on-line monitoring of water chemistry and corrosion control in water cooled power reactors. Vienna: International Atomic Energy Agency; 2002. (IAEA TECDOC-1303).
   Google Scholar
• Liu C, Macdonald DD. An advanced Pd/Pt relative resistance sensor for the continuous monitoring of dissolved hydrogen in aqueous systems at high subcritical and supercritical temperature. J Supercrit Fluid. 1995;8:263–270.
   Web of Science ®Google Scholar
• Uchida S, Satoh T, Kakinuma N, Miyazawa T, Satoh Y, Makela K. An electrochemical sensor array for in-situ measurements of oxide film electric resistance in high temperature water. ECS Trans. 2007;2(25):39–50.
   Google Scholar
• Asakura Y, Nagase M, Sakagami M, Uchida S. In-line monitor for electrical conductivity of high temperature aqueous environments. J Electrochem Soc. 1989;136:3309–3313.
   Web of Science ®Google Scholar
• Tachibana K. Pressure-balance pH sensing system for high temperature and high pressure water. Materia Japan. 1995;34:1227–1232. Japanese.
   Google Scholar
• Hara N, Sugimoto K. A Nb-doped TiO2 semiconductor pH sensor for use in high temperature aqueous solutions. J Electrochem Soc. 1990;137(8):2517–2523.
   Web of Science ®Google Scholar
• Nagata N. In core measurement of electrochemical corrosion potential in Tsuruga-2. Paper presented at: International Workshop on Optimization of Dissolved Hydrogen Content in PWR Primary Coolant; 2007 Jul 18–19; Sendai: Tohoku University. ( Paper 16).
   Google Scholar
• Ashida S, Takagi J, Ichikawa N. First experience of hydrogen water chemistry at Japanese BWRs. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems 6; 1992 Oct 12–15; Bournemouth: British Nuclear Energy Society.
   Google Scholar
• Takiguchi H, Sekiguchi S, Abe A, Akamine K, Sakai M, Wada Y, Uchida S. Evaluation of effectiveness of hydrogen water chemistry for different types of boiling water reactors. J Nucl Sci Technol. 1999;36(2):179–188.
   Web of Science ®Google Scholar
• Bosch RW, Kerner Z, Nagy G, Feron D, Navas M, Bogaerts W, Karnik D, Dorsch T, Kilian R, Ullberg M, Molander A, Makela K, Saario T. LIRES; European sponsored research project to develop light water reactor reference electrode. Paper presented at: EUROCORR2003; 2003 Sep 26 to Oct 2; Budapest: European Federation of Corrosion.
   Google Scholar
• McKeen K, Lalonde M, Scott A, Ross J. Hydrogen effusion probe development and installation at the Point Lepreau Generating Station. Paper presented at: 28th Annual Conference of the Canadian Nuclear Society; 2007 Jun 3–6; St. John: Canadian Nuclear Society.
   Google Scholar
• Aiken J. New Brunswick innovation to assist energy challenges. RPC Tech. release; 2007 Nov 27. Fredericton: Research and Productivity Council, Fredericton, New Brunswick, Canada.
   Google Scholar
• Bojinov M. Development of electrochemical techniques to study oxide films on construction materials in high temperature water. Paper presented at: JAIF International Conference on Water Chemistry in Nuclear Power Plants; 1998 Oct 13–16; Kashiwazaki: Japan Atomic Industrial Forum.
   Google Scholar
• Bojinov M, Laitinen T, Makela K, Saario T. A conduction mechanism of the passive film on iron based on contact electric impedance and resistance measurement. J Electrochem Soc. 2001;148:B243–B250.
   Web of Science ®Google Scholar
• Hickling J, Taylor DF, Andresen PL. Use of electrochemical noise to detect stress corrosion crack initiation in simulated BWR environments. Mater Corrosion. 1998;49:651–658.
   Web of Science ®Google Scholar
• Liu C, Macdonald DD, Medina E, Villa JJ, Bueno JM. Probing corrosion activity in high subcritical and supercritical water through electrochemical noise analysis. Corrosion. 1994;50:687–694.
   Web of Science ®Google Scholar
• Catlin WR, Lord DC, Prater TA, Coffin LF. The reversing D-C electric potential method. In: Cullen WH, Landgraf RW, Kaisand LR, Underwood JH, editors. Automated test methods for fracture and fatigue crack growth, ASTM STP, 887, 67. Philadelphia (PA): American Society for Testing and Materials; 1985.
   Google Scholar
• Weinstein D. Real time in reactor monitoring of double cantilever beam crack growth sensors. Paper presented at: 6th International Symposium on Environmental Degradation of Materials in Nuclear Power Systems – Water Reactors; 1993 Aug 1–6; San Diego (CA): American Nuclear Society; p. 645–650.
   Google Scholar
• IAEA. Coolant technology of water cooled reactors. Vienna: International Atomic Energy Agency; 1992. (IAEA-TECDOC-667).
   Google Scholar
• IAEA. High temperature on-line monitoring of water chemistry and corrosion control in water cooled power reactors. Vienna: International Atomic Energy Agency; 2002. (IAEA-TECDOC-1303).
   Google Scholar
• IAEA. Data processing technologies and diagnostics for water chemistry and corrosion in nuclear power plants. Vienna: International Atomic Energy Agency; 2006. (IAEA-TECDOC-1505).
   Google Scholar
• Uchida S, Satoh T, Iinuma K, Satoh Y. Effects of hydrogen peroxide on intergranular stress corrosion cracking of stainless steel. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems; 2004 Oct 11–14; San Francisco (CA): EPRI, p. 518–527. [ CD-ROM].
   Google Scholar
• Ishida K, Lister DH. In-situ measurement of corrosion of type 316 stainless steel in 280 ºC pure water via the electrical resistance of a thin wire. J Nucl Sci Technol. 2012;49(11):1078–1091.
   Web of Science ®Google Scholar
• Turner C, Guzonas D. Improving chemistry performance in CANDU® plants. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems, NPC 2010; 2010 Oct 3–7; Quebec: Canadian Nuclear Society. [ CD-ROM].
   Google Scholar
• Lu YC. Define optimum conditions for steam generator tube integrity and an extended service life. Paper presented at: 15th International Conference on Nuclear Engineering ICONE-15-10854; 2007 Apr 22–26; Nagoya: Japan Society of Mechanical Engineers.
   Google Scholar
• IAEA. Fuel cladding interaction with water coolant in power reactors. Vienna: International Atomic Energy Agency; 1988. (IAEA-TECDOC-356).
   Google Scholar
• Takiguchi H, Takamatsu H, Uchida S, Ishigure K, Nakagami M, Matsui M. Water chemistry data acquisition, processing, evaluation and diagnostic systems in light water reactors. J Nucl Sci Technol. 2004;41(2):214–225.
   Web of Science ®Google Scholar
• Millett P. PWR steam chemistry considerations – position paper. Appendix B.2 in pressurized water reactor secondary water chemistry guidelines – revision 6. Palo Alto (CA): Electric Power Research Institute; 2004. ( Final Report 1008224).
   Google Scholar
• Srisukvatananan P, Lister DH, Svoboda B, Daucik K. Assessment of the state of the art of sampling corrosion products from water/steam cycles. Power Plant Chem. 2007;9(10):613–626.
   Google Scholar
• Cook WG, Lister D.H, McInerney JM. The effects of high liquid velocity and coolant chemistry on material transport in PWR coolants. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems 8; 2000 Oct 22–26; Bournemouth: British Nuclear Energy Society.
   Google Scholar
• Tremaine PR, LeBlanc JC. The solubility of magnetite and the hydrolysis and oxidation of Fe2+ in water to 300 ºC. J Solution Chem. 1980;9:415–442.
   Web of Science ®Google Scholar
• Large NR, Harper A, Ashmore CB, Beckett NA, Nichols JL, Johnson PAV, Bridle D.A, Cake P. Sampling effects associated with PWR primary circuit soluble corrosion product measurements: an experimental and modelling study. Paper presented at: JAIF International Conference on Water Chemistry in Nuclear Power Plants; 1991 Apr 22–25; Fukui: Japan Atomic Industrial Forum.
   Google Scholar
• Large NR, Mead S, Nichols JL, Patel NM, Lawson D, Beckett NA. Studies of problems of corrosion product sampling from PWR primary coolant. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems 5; 2000 Oct 22–26; Bournemouth: British Nuclear Energy Society.
   Google Scholar
• Lister DH, Srisukvatananan P, Uchida S. Sampling nuclear reactor coolant systems. Paper presented at: 14th International Conference on the Properties Of Water and Steam; 2013 Sep 1–5; Greenwich: International Association for Properties of Water and Steam.
   Google Scholar
• Svoboda R, Ziffermayer G, Romanelli S, Kaufamm W, Sozzi L, Schaefer ME. Trace analysis of corrosion products by integrated sampling techniques. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems 3; 1983 Oct 17–21; Bournemouth: British Nuclear Energy Society.
   Google Scholar
• Svoboda R, Ziffermayer G, Romanelli S, Seipp HG, Kaufamm W. Design measures for control of corrosion products in the feedwater of LWR plants. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems 3; 1983 Oct 17–21; Bournemouth: British Nuclear Energy Society.
   Google Scholar
• Polley NV, Andersson PO. Study of the integrity of radioisotope sampling from the primary coolant of Ringhals 3 PWR. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems 5; 1989 Oct 23–27; Bournemouth; British Nuclear Energy Society.
   Google Scholar
• Polley NV. Corrosion product and particulate sampling from the Sizewell B primary coolant. TEPZ/REP/0101/93: PWR/CTG/P(93)106; 1993 Dec; Nuclear Electric.
   Google Scholar
• Garbett K. Elemental and radionuclide corrosion product monitoring at Sizewell B PWR. Paper presented at: PWR Primary Water Chemistry Guidelines Revision Meeting; 1998 Feb 3–8; Clearwater Beach (FL): Electric Power Research Institute.
   Google Scholar
• Garbett K, Corrosion product behaviour in the Sizewell B PWR. Proceedings of the International Conference on Water Chemistry of Nuclear Reactor Systems 8; 2000 Oct 22–26; Bournemouth: British Nuclear Society.
   Google Scholar
• Barton M, Conqueror MR, Garbett K, Mantell MA, Phillips ME, Polley MV, Westall WA. Corrosion product measurements at the Sizewell B PWR. Proceedings of the International Conference on Water Chemistry of Nuclear Reactor Systems 8; 2000 Oct 22–26; Bournemouth: British Nuclear Society.
   Google Scholar
• EPRI. Survey of iron and nickel concentrations in PWR primary coolant. Palo Alto (CA): Electric Power Research Institute; 2001. ( EPRI 1003136).
   Google Scholar
• EPRI. Sampling considerations for monitoring corrosion products in the reactor coolant system in pressurized water reactors. Palo Alto (CA): Electric Power Research Institute; 2006. (EPRI 1013668).
   Google Scholar
• IAPWS. Technical guidance document: corrosion product sampling and analysis for fossil and combined cycle plants. London: International Association for the Properties of Water and Steam; 2014. Available from: http://www.iapws.org
   Google Scholar
• van Eeden N, Galt KJ. Corrosion product sampling at Koeberg nuclear power station. Power Plant Chem. 2006;8(3):159–168.
   Google Scholar
• Jonas O, Mancini JM. Sampling savvy. Power Eng. May 2005;52--59. Available from www.power.eng.com
   Google Scholar
• ASTM. Standard practices for sampling water from closed conduits. Designation: D 3370–95a (reapproved 2003). Philadelphia (PA): American Society for Testing and Materials International; 2004.
   Google Scholar
• Srisukvatananan P, Lister DH, Svoboda R, Daucik K. A CFD study of corrosion product collection efficiency of sampling nozzles under power plant conditions. Power Plant Chem. 2009;11(10):576–581.
   Google Scholar
• Wagner W. Praktische strömungstechnik. Gräfelfing bei München: Kommissionsverlag Technischer Verlag Resch KG; 1976.
   Google Scholar
• Killeen J, Nordmann F, Schunk J, Vonkova K. Optimisation of water chemistry to ensure reliable water reactor fuel performance at high burnup and in ageing plant (FUWAC): an International Atomic Energy Agency coordinated research project. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems, NPC 2010; 2010 Oct 3–7; Quebec: Canadian Nuclear Society. [ CD-ROM].
   Google Scholar
• Nordmann F, Odar S, Venz H, Kysela J, Ruehle W, Reiss R. ANT International chemistry update and best practices. Paper presented at: International Conference on Water Chemistry of Nuclear Reactor Systems, NPC 2010; 2010 Oct 3–7; Quebec: Canadian Nuclear Society. [ CD-ROM].
   Google Scholar
• IAPWS. Technical guidance document: volatile treatments for the steam–water circuits of fossil and combined cycle/HRSG power plants. London: International Association for the Properties of Water and Steam; 2010. Available from: http://www.iapws.org
   Google Scholar