Механизмы и главные причины повреждений тепловыделяющих элементов и тепловыделяющих сборок атомных электрических станций с реакторами с водой под давлением
Ключевые слова:
топливный цикл, выгорание, фреттинг-износ, акустика, вибрация, повышение безопасности
Аннотация
Представлена первая часть обзора публикаций по проблеме повышения эксплуатационного ресурса и надёжности тепловыделяющих сборок (ТВС) и элементов (ТВЭЛ). В следующих выпусках будут опубликованы вторая — о динамических взаимодействиях потока теплоносителя с ТВС и третья части — о прогнозировании виброакустических резонансов в активных зонах АЭС с ВВЭР. Приведены результаты исследования причин и механизмов отказов ТВЭЛов, при которых радиоактивные материалы (газообразные продукты деления и летучие элементы, в частности, криптон, ксенон, йод, цезий) попадают из топливной таблетки в первый контур охлаждения реактора. Показано, что на уровень разгерметизации ядерного топлива оказывают влияние все стадии жизненного цикла изделий: проектирование, производство, эксплуатация, вибрации ТВС.
Известно, что TBC представляет собой гидроупругую колебательную систему, состоящую из механической и гидродинамической взаимодействующих подсистем, и ее вибрации обусловлены происходящими в них динамическими процессами. Отмечается, что гидродинамическая подсистема изучена в значительной мере недостаточно, ввиду сложности описания процессов формирования случайных гидродинамических нагрузок на обтекаемые поверхности, а также влияния теплогидравлических и акустических характеристик потока на возникновение самовозбуждающихся колебаний. Исходя из данных по эксплуатации дефектных ТВС, оценены длительности эксплуатации негерметичных ТВЭЛов и их линейные мощности. Описана эволюция условий эксплуатации топлива и изменения конструкции топлива. Упомянуты имеющиеся рекомендации по оптимизации проектов ТВС, выработанные с учетом опыта эксплуатации реакторов и результатов проведенных исследований по фреттинг-износу. Показано что борьбу за качество топлива ведут все, кто его производит и эксплуатирует, поскольку это основной показатель поставщика топлива и АЭС на мировом рынке. Наиболее важными критериями качества ядерного топлива являются удлинение топливных циклов и повышение выгорания при сохранении или даже повышении уровня безопасности. В настоящее время проект «Нулевой уровень отказа ядерного топлива» находится в стадии реализации и получении первых результатов совместной деятельности всех участников.
Литература
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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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40. El-Adham K. Fuel Failure Mechanisms in Operating US Plants from 1981 to 1986.J. Nucl. Safety. 1988;152;2—3:344—355.
41. Outlook On Advanced Reactors. Nucleonics Week. 1989:1—11.
42. Nuclear Power Experience. V. BWR-2. I. Fuel, 1990:24—25.
43. Jonsson A., Sundstrom U., Hallstradius L. Inreactor Mechanical Performance of BWR Fuel Channels. Proc. Int. Top. Mtg LWR Fuel Performance. Avignon, 1991;1;184:1—6.
44. Chapot J., Freire J. Tracing Fuel Failures at Angra 1. J. Nucl. Eng. Int. 1994;32:17—21.
45. Chapot J.L.C., Suano R., de Couto N. Fuel Failures at ANGRA 1: Cause and mitigation. Vienna: IAEA, 2003.
46. Provost J.L., Debes M. EDF PWR Fuel Operating Experience and High Burnup Performances. Brussels: Top Fuel, 2006.
47. Nuclear Power Experience. Washington: Hagler Bailly, Inc., 1994. V. PWR-2.I.;79.
48. Nuclear Fuel. N.-Y.: McGraw-Hill, 1993;5;3.
49. Nuclear Fuel. N.-Y.: McGraw-Hill, 1994;5;3.
50. Wilson H.W. e. a. Westinghouse Fuel Performance in Today’s Aggressive Plant Operating Environment. Int. Topical Mtg on Light Water Reactor Fuel Performance. Portland, ANS, Le Grange, 1997.
51. Nuclear Power Experience. Washington: Hagler Bailly, Inc., 1993;PWR-2;75.
52. Baillon N. Grid to Rod Wear in EDF PWR — From Operating Problems to New Design Qualification Method. Vienna: IAEA, 2005.
53. Woods K.N., Klinger W. Siemens Fuel Performance Overview. Proc. Int. Topical Mtg on LWR Fuel Performance. Portland, 1997.
54. Billerey A. Evolution of the Fuel Rod Support Under Irradiation and it Impacts on the Mechanical Behavior of the Fuel Assemblies. Vienna: IAEA, 2005.
55. Klinger W., Petit C., Willse J. Experience and Reliability of FRAMATOME ANP’S PWR and BWR fuel. Vienna: IAEA, 2003.
56. Blanc C., Bournay P., Dangouleme D. FRAGEMA fuel reliability. Proc. Int. Top. Mtg on LWR Fuel Performance. 1991;1:353—360.
57. Knott R.P., Keterson R.L., Hallstadius L.G., Young M.Y. Advanced PWR Fuel Designs for High Duty Operation. Int. Conf. Top Fuel. Würzburg, 2003.
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.
13. Pickman D.O. Internal Cladding Corrosion Effects // J. Nucl. Eng. Design. 1975. V. 33. Iss. 2. Pp. 141—154.
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38. Review of Fuel Failures in Water Cooled Reactors. Nuclear Energy Series No. NF-T-2.1. IAEA: Vienna, 2010.
39. Garzarolli F., Von Jan R., Stehle H. The Main Causes of Fuel Element Failure in Water-cooled Power Reactors // At. Energy Rev. 1979. V. 17. No. 1. Pp. 31—128.
40. El-Adham K. Fuel Failure Mechanisms in Operating US Plants from 1981 to 1986 // J. Nucl. Safety. 1988. V. 152. No. 2—3. Pp. 344—355.
41. Outlook On Advanced Reactors // Nucleonics Week. 1989. Pp. 1—11.
42. Nuclear Power Experience. V. BWR-2. I. Fuel, 1990. Pр. 24—25.
43. Jonsson A., Sundstrom U., Hallstradius L. Inreactor Mechanical Performance of BWR Fuel Channels // Proc. Int. Top. Mtg LWR Fuel Performance. Avignon, 1991. V. 1. No. 184. Pp. 1—6.
44. Chapot J., Freire J. Tracing Fuel Failures at Angra 1 // J. Nucl. Eng. Int. 1994. No. 32. Pp. 17—21.
45. Chapot J.L.C., Suano R., de Couto N. Fuel Failures at ANGRA 1: Cause and mitigation. Vienna: IAEA, 2003.
46. Provost J.L., Debes M. EDF PWR Fuel Operating Experience and High Burnup Performances. Brussels: Top Fuel, 2006.
47. Nuclear Power Experience. Washington: Hagler Bailly, Inc., 1994. V. PWR-2.I. No. 79.
48. Nuclear Fuel. N.-Y.: McGraw-Hill, 1993. V. 5. No. 3.
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50. Wilson H.W. e. a. Westinghouse Fuel Performance in Today’s Aggressive Plant Operating Environment // Int. Topical Mtg on Light Water Reactor Fuel Performance. Portland, ANS, Le Grange, 1997.
51. Nuclear Power Experience. Washington: Hagler Bailly, Inc., 1993. V. PWR-2. No. 75.
52. Baillon N. Grid to Rod Wear in EDF PWR — From Operating Problems to New Design Qualification Method. Vienna: IAEA, 2005.
53. Woods K.N., Klinger W. Siemens Fuel Performance Overview // Proc. Int. Topical Mtg on LWR Fuel Performance. Portland, 1997.
54. Billerey A. Evolution of the Fuel Rod Support Under Irradiation and it Impacts on the Mechanical Behavior of the Fuel Assemblies. Vienna: IAEA, 2005.
55. Klinger W., Petit C., Willse J. Experience and Reliability of FRAMATOME ANP’S PWR and BWR fuel. Vienna: IAEA, 2003.
56. Blanc C., Bournay P., Dangouleme D. FRAGEMA fuel reliability // Proc. Int. Top. Mtg on LWR Fuel Performance. 1991. V. 1. Pp. 353—360.
57. Knott R.P., Keterson R.L., Hallstadius L.G., Young M.Y. Advanced PWR Fuel Designs for High Duty Operation // Int. Conf. Top Fuel. Würzburg, 2003.
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. Pp. 121—127.
65. Paııdousis M.P. A Review of Flow-induced Vibrations in Reactors and Reactor Components // Nuclear Eng. and Design. 1982. V. 74. Pp. 31—60.
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67. Ikeno T., Kajishima T. Decay of Swirling Turbulent Flow in Rod-bundle // J. Fluid Sci. and Techn. 2006. V. 1(1). Pp. 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. V. 239. Pp. 2820—2824.
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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83. Перевезенцев В.В., Солонин В.И., Сорокин Ф.Д Нестационарные гидродинамические нагрузки и вибрации пучка ТВЭЛов в ТВС ВВЭР-440 // Известия вузов. Серия «Ядерная энергетика». 2008. № 4. С. 23—29.
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87. Шульга И. Тепловыделяющие разборки // Атомный эксперт. 2018. № 3 [Электрон. ресурс] http:// atomicexpert.com/page3174296.html (дата обращения 25.12.2018).
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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.
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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.
Опубликован
2019-01-26
Выпуск
Раздел
Ядерные энергетические установки, включая проектирование, эксплуатацию и вывод из эксплуатации (05.14.03)
