Mechanisms and Main Causes of Damages Inflicted to Fuel Rods and Fuel Assemblies at Nuclear Power Plants Equipped with Pressurized Water Reactors
DOI:
https://doi.org/10.24160/1993-6982-2019-4-34-49Keywords:
fuel cycle, burnup, fretting wear, acoustics, vibration, safety improvementAbstract
This article is the first part of the review of publications on the problem of increasing the service life and improving the reliability of fuel assemblies (FA) and fuel rods (FR). In the next issues of the journal, Part 2 "Dynamic interactions between the coolant flow and FAs" and Part 3 "Prediction of vibroacoustic resonances in the reactor cores of VVER-based nuclear power plants" of this review will be published. This review part presents the results from investigations into the causes and mechanisms of FR failures, in which radioactive materials (gaseous fission products and volatile elements, in particular, krypton, xenon, iodine, and cesium) escape from the fuel pellet into the reactor primary coolant circuit. It is shown that the nuclear fuel depressurization level is influenced by all stages of the product life cycle, including design, manufacture, and operation of FAs. In particular, during operation, FA vibrations have an effect on the nuclear fuel depressurization level.
As is well-known, an FA is a hydroelastic oscillatory system consisting of two interacting subsystems: a mechanical one and a hydrodynamic one. The FA vibration is due to the dynamic processes occurring in these subsystems. It is noted that the hydrodynamic subsystem has been studied to a rather insufficient extent, which is due to complexity of describing the processes through which the random hydrodynamic loads applied to the streamlined surfaces are produced, as well as the influence of flow thermal-hydraulic and acoustic characteristics on the occurrence of self-excited oscillations. Based on the defective FA operation data, the service life of leaky fuel rods and their linear heat generation rates are estimated. The evolutions of fuel operation conditions and fuel design changes are described. The available recommendations on optimizing FA designs developed taking into account the experience gained from operation of the reactors and the results of the accomplished fretting wear investigations are mentioned. It is shown that all who manufacture and operate nuclear fuel take efforts aimed at improving its quality, because it is the key indicator characterizing the vendor of fuel and nuclear power plants in the world market. Achieving longer fuel campaigns and higher burnup values while keeping or even improving the safety level are the most important criteria for nuclear fuel quality. Currently, the project called Nuclear Fuel Zero Failure Level is in the stage of implementation and obtaining the first results of joint activities of all participants.
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Для цитирования: Проскуряков К.Н., Аникеев А.В. Механизмы и главные причины повреждений тепловыделяющих элементов и сборок атомных электрических станций с реакторами с водой под давлением // Вестник МЭИ. 2019. № 4. С. 34—49. DOI: 10.24160/1993-6982-2019-4-34-49.
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58. Scott D. e. a. Post-irradiation Examination of the Lead Westinghouse Robust Fuel Assemblies After Three Cycles of Operation in the Wolf Creek Generating Station. Int. Conf. Top Fuel. Würzburg, 2003.
59. Vallory J. Methodology of PWR Fuel Rod Vibration and Evaluation in HERMES Facilities. Vienna: IAEA, 2005.
60. Gottuso D., Canat J.N., Mollard P. A Family of Upgraded Fuel Assemblies for PWR. Int. Conf. Top Fuel. Salamanca, 2006.
61. Nakajima I., Teshima H., Yamada M. Improvement and Innovation of Mitsubishi PWR Fuel. Int. Conf., Top Fuel. Kyoto, 2005.
62. Kennard M.W. Nuclear Fuel Performance, Trends, Remedies and Challenges. Int. Conf. Top Fuel. Salamanca, 2006.
63. Strasser A., Gingold J. Evaluation of Debris Failures and Preventive Methods. Proc. Fuel Failure in Normal Operation of Water Reactors: Experience, Mechanisms and Management. IAEA-TECDOC-709. Dimitrovgrad, 1993.
64. Carter J., Manzer A.M. Overview of Defect Mechanisms in CANDU Fuel. Proc. Fuel Failure in Normal Operation of Water Reactors: Experience, Mechanisms and Management. IAEA-TECDOC-709. Dimitrovgrad, 1992:121—127.
65. Paııdousis M.P. A Review of Flow-induced Vibrations in Reactors and Reactor Components. Nuclear Eng. and Design. 1982;74:31—60.
66. Pettigrew M.J., Carlucci L.N., Taylor C.E., Fi- sher N.J. Flow-induced Vibration and Related Technologies in Nuclear Technologies. Nuclear Eng. and Design. 1991;131:81—100.
67. Ikeno T., Kajishima T. Decay of Swirling Turbulent Flow in Rod-bundle. J. Fluid Sci. and Techn. 2006;1(1):36—47.
68. Benhamadouche S., Moussou P., Maitre C.L. CFD Estimation of the Flow-Induced Vibrations of a Fuel Rod Downstream of a Mixing Grid. Proc. Pressure Vessels and Piping Conf. Prague, 2009.
69. Kim K.-T. The Study on Grid-to-rod Wear Models for PWR Fuel. Nuclear Eng. and Design. 2009;239: 2820—2824.
70. Kim K.-T. A Study on the Grid-to-rod Wearinduced Fuel Failure Observed in the 16×16 KOFA Fuel. Nuclear Engineering and Design. 2010;240:756—762.
71. Kim K.-T. The Effect of Fuel Rod Supporting Conditions on Fuel Rod Vibration Characteristics and Grid-to-rod Wear. Nuclear Eng. and Design. 2010;240: 1886—1391.
72. Conner M. E., Baglietto E., Elmahdi A.M. CFD Methodology and Validation for Single-phase Flow in PWR Fuel Assemblies. Ibid:2088—2095.
73. Yan J., Yuan K., Tatli E., Karoutas Z. A new Method to Predict Grid-to-rod in a PWR Fuel Assembly Inlet Region. Nuclear Eng. and Design. 2011;241:2974—2982.
74. Bhattachary A., Yu S.D., Kawall G. Numerical Simulation of Turbulent Flow Through a 37 Element CANDU Fuel Bundle. Annals Nuclear Energy. 2012;40 (1): 87—105.
75. Delafontain S., Ricciardi G. Fluctuating Pressure Calculation Induced by Axial Flow Through Mixing Grid. Nuclear Eng. and Design. 2012;242:233—246.
76. Lui Z. G., Liu Y., Lu J. Numerical Simulation of the Fluid-structure Interaction for Two Simple Fuel Assemblies. Nuclear Eng. and Design. 2013;243:1—12.
77. Mohany A., Hassan M. Modeling of Fuel Bundle Vibration and the Associated Wear in a CANDU Fuel Channel. Ibid:214—222.
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For citation: Proskuryakov K.N., Anikeev A.V. Mechanisms and Main Causes of Damages Inflicted to Fuel Rods and Fuel Assemblies at Nuclear Power Plants Equipped with Pressurized Water Reactors. Bulletin of MPEI. 2019;4:34—49. (in Russian). DOI: 10.24160/1993-6982-2019-4-34-49.
2. Strasser A., Sunderland D. A Review of Recent LWR Fuel Failures // Proc. Fuel Failure in Normal Operation of Water Reactors: Experience, Mechanisms and Management. IAEA-TECDOC-709. Dimitrovgrad, 1993. Pp. 17—25.
3. Dumont A. FRAGEMA Fuel Reliability: from Detection of Fuel Failures to the Feedback on Design and Fabrication // Ibid. Pp. 46—50.
4. Von Jan R. Siemens KWU Experience with LWR Fuel: Failure Evaluation, Mechanisms and Remedies // Ibid. Pp. 50—57.
5. Lundholm L., Grapengiesser B., Schrire D., Hallstadius L. ABB Atom Fuel Failure — an Overview // Ibid. Pp. 57—63.
6. Yang R., Ozer O., Rosenbaum H.S. Current Challenges and Expectations of High Performance Fuel for the Millennium // Proc. 2000 Intern. Topical Meeting on LWR Fuel Performance. Park City, 2000.
7. Klinger W., Petit C., Willse J. Experience and Reliability of Framatome ANP’s PWR and BWR fuel // Proc. Tech. Meeting Fuel Failure in Water Reactors: Causes and Mitigation. Bratislava, 2003. Pp. 21—29.
8. Conde Lopez J.M., Garcia Leiva M. Spanish Experience with LWR Fuel: General Overview // Ibid. Pp. 30—40.
9. Andersson T. Fuel Failure Mitigation at the Ringhals Рlant // Ibid. Pp. 123—133.
10. Yang R. e. a. Fuel R&D to Improve Fuel Reliability // Proc. 2005 Water Reactor Fuel Performance Meeting. Kyoto, 2005. Pp. 8—14.
11. Dubrovin K.P., Fatieva N.L., Smirnov V.P. Data of Leaking Fuel Assemblies in LWRs Operated in the Former USSR // Proc. Fuel Failure in Normal Operation of Water Reactors: Experience, Mechanisms and Management. IAEA-TECDOC-709. Dimitrovgrad, 1993. Pp. 106—112.
12. Clayton I.C. Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods. Review Rep. Vienna: Intern. Atomic Energy Agency, 1987.
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59. Vallory J. Methodology of PWR Fuel Rod Vibration and Evaluation in HERMES Facilities. Vienna: IAEA, 2005.
60. Gottuso D., Canat J.N., Mollard P. A Family of Upgraded Fuel Assemblies for PWR // Int. Conf. Top Fuel. Salamanca, 2006.
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63. Strasser A., Gingold J. Evaluation of Debris Failures and Preventive Methods // Proc. Fuel Failure in Normal Operation of Water Reactors: Experience, Mechanisms and Management. IAEA-TECDOC-709. Dimitrovgrad, 1993.
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68. Benhamadouche S., Moussou P., Maitre C.L. CFD Estimation of the Flow-Induced Vibrations of a Fuel Rod Downstream of a Mixing Grid // Proc. Pressure Vessels and Piping Conf. Prague, 2009.
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70. Kim K.-T. A Study on the Grid-to-rod Wear-induced Fuel Failure Observed in the 16×16 KOFA Fuel // Nuclear Engineering and Design. 2010. V. 240. Pp. 756—762.
71. Kim K.-T. The Effect of Fuel Rod Supporting Conditions on Fuel Rod Vibration Characteristics and Grid- to-rod Wear // Nuclear Eng. and Design. 2010. V. 240. Pp. 1886—1391.
72. Conner M. E., Baglietto E., Elmahdi A.M. CFD Methodology and Validation for Single-phase Flow in PWR Fuel Assemblies // Ibid. Pp. 2088—2095.
73. Yan J., Yuan K., Tatli E., Karoutas Z. A new Method to Predict Grid-to-rod in a PWR Fuel Assembly Inlet Region // Nuclear Eng. and Design. 2011. V. 241. Pp. 2974—2982.
74. Bhattachary A., Yu S.D., Kawall G. Numerical Simulation of Turbulent Flow Through a 37 Element CANDU Fuel Bundle // Annals Nuclear Energy. 2012. V. 40 (1). Pp. 87—105.
75. Delafontain S., Ricciardi G. Fluctuating Pressure Calculation Induced by Axial Flow Through Mixing Grid // Nuclear Eng. and Design. 2012. V. 242. Pp. 233—246.
76. Lui Z. G., Liu Y., Lu J. Numerical Simulation of the Fluid-structure Interaction for Two Simple Fuel Assemblies // Nuclear Eng. and Design. 2013. V. 243. Pp. 1—12.
77. Mohany A., Hassan M. Modeling of Fuel Bundle Vibration and the Associated Wear in a CANDU Fuel Channel // Ibid. Pp. 214—222.
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Для цитирования: Проскуряков К.Н., Аникеев А.В. Механизмы и главные причины повреждений тепловыделяющих элементов и сборок атомных электрических станций с реакторами с водой под давлением // Вестник МЭИ. 2019. № 4. С. 34—49. DOI: 10.24160/1993-6982-2019-4-34-49.
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1. RB-057-10. Polozhenie o Proektirovanii i Izgotovlenii Teplovydelyayushchih Elementov i Teplovydelyayushchih Sborok s Uran-plutonievym (Moks) Toplivom. Yadernaya i Radiatsionnaya Bezopasnost'. 2010;4 (58): 13—33. (in Russian).
2. Strasser A., Sunderland D. A Review of Recent LWR Fuel Failures. Proc. Fuel Failure in Normal Operation of Water Reactors: Experience, Mechanisms and Management. IAEA-TECDOC-709. Dimitrovgrad, 1993:17—25.
3. Dumont A. FRAGEMA Fuel Reliability: from Detection of Fuel Failures to the Feedback on Design and Fabrication. Ibid:46—50.
4. Von Jan R. Siemens KWU Experience with LWR Fuel: Failure Evaluation, Mechanisms and Remedies. Ibid:50—57.
5. Lundholm L., Grapengiesser B., Schrire D., Hallstadius L. ABB Atom Fuel Failure — an Overview. Ibid:57—63.
6. Yang R., Ozer O., Rosenbaum H.S. Current Challenges and Expectations of High Performance Fuel for the Millennium. Proc. 2000 Intern. Topical Meeting on LWR Fuel Performance. Park City, 2000.
7. Klinger W., Petit C., Willse J. Experience and Reliability of Framatome ANP’s PWR and BWR fuel. Proc. Tech. Meeting Fuel Failure in Water Reactors: Causes and Mitigation. Bratislava, 2003:21—29.
8. Conde Lopez J.M., Garcia Leiva M. Spanish Experience with LWR Fuel: General Overview. Ibid: 30—40.
9. Andersson T. Fuel Failure Mitigation at the Ringhals Рlant. Ibid:123—133.
10. Yang R. e. a. Fuel R&D to Improve Fuel Reliability. Proc. 2005 Water Reactor Fuel Performance Meeting. Kyoto, 2005:8—14.
11. Dubrovin K.P., Fatieva N.L., Smirnov V.P. Data of Leaking Fuel Assemblies in LWRs Operated in the Former USSR. Proc. Fuel Failure in Normal Operation of Water Reactors: Experience, Mechanisms and Management. IAEA-TECDOC-709. Dimitrovgrad, 1993:106—112.
12. Clayton I.C. Internal Hydriding in Irradiated Defected Zircaloy Fuel Rods. Review Rep. Vienna: Intern. Atomic Energy Agency, 1987.
13. Pickman D.O. Internal Cladding Corrosion Effects. J. Nucl. Eng. Design. 1975;33;2:141—154.
14. Perepelkin S.O. i dr. Rezul'taty Poslereaktornyh Issledovaniy Negermetichnyh TVELov VVER. Reaktornoe Materialovedenie: Tezisy Dokl. VIII Rossiyskoy Konf. Dimitrovgrad: FGUP «GNTS RF NIIAR», 2007:16—19. (in Russian).
15. Perepelkin S.O. i dr. Rezul'taty Poslereaktornyh Issledovaniy Negermetichnyh TVELov VVER. Bezopasnost', Effektivnost' i Ekonomika Atomnoy Energetiki: Tezisy Dokl. VI Mezhdunar. Nauch.-tekhn. Konf. M.: OAO «Kontsern Rosenergoatom», 2008. (in Russian).
16. Markov D.V. e. a. Results of Post Irradiation Examinations of WER Leaky Rods. Proc. Top Fuel Conf. Paris, 2009:164—172.
17. Perepelkin C.O. i dr. Rezul'taty Poslereaktornyh Issledovaniy Negermetichnyh TVELov VVER. Sbornik trudov. Dimitrovgrad: FGUP «GNTS RF NIIAR», 2007;4:12—21. (in Russian).
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19. Wilson H., Miller H., Kunishi H. Westinghouse Fuel Performance Experience. Fuel Failure in Normal Operation of Water Reactors: Experience, Mechanisms and Management. IAEA-TECDOC-709. Dimitrovgrad, 1993:133—137.
20. Lundberg S. Experience with Defect Fuel at the Kemkraftwerk Leibstadt: Detection, Inspection, Handling and Management. Ibid:156—168.
21. Kennard M., Sunderland D., Harbottle J. A Study of Grid-to Rod Fretting Wear in PWR Fuel Assembly. Stoller Rep, 1995.
22. Kim K. e. a. Fuel Failure Analysis of Kori-2 Cycle 8. Daejeon: Korea Atomic Energy Research Institute, 1993.
23. Donovan K. Fuel Integrity Initiative Overview. Proc. ANS LWR Fuel Performance Conf. San Francisco, 2007.
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For citation: Proskuryakov K.N., Anikeev A.V. Mechanisms and Main Causes of Damages Inflicted to Fuel Rods and Fuel Assemblies at Nuclear Power Plants Equipped with Pressurized Water Reactors. Bulletin of MPEI. 2019;4:34—49. (in Russian). DOI: 10.24160/1993-6982-2019-4-34-49.
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2019-01-26
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Nuclear Power Plants, Including Design, Operation and Decommissioning (05.14.03)
