본문 바로가기
KERD
논문KCI 등재

Analysis of activated colloidal crud in advanced and modular reactor under pump coastdown with kinetic corrosion

2

조회

0

다운로드

1

인용

0

참고문헌

키워드

주제분류원자력공학

초록

The analysis of rapid flow transients in Reactor Coolant Pumps (RCP) is essential for a reactor safety study. An accurate and precise analysis of the RCP coastdown is necessary for the reactor design. The coastdown of RCP affects the coolant temperature and the colloidal crud in the primary coolant. A realistic and kinetic model has been used to investigate the behavior of activated colloidal crud in the primary coolant and steam generator that solves the pump speed analytically. The analytic solution of the non-dimensional flow rate has been determined by the energy ratio b. The kinetic energy of the coolant fluid and the kinetic energy stored in the rotating parts of a pump are two essential parameters in the form of b. Under normal operation, the pump's speed and moment of inertia are constant. However, in a coastdown situation, kinetic damping in the interval has been implemented. A dynamic model ACCP-SMART has been developed for System Integrated Modular and Advanced Reactor (SMART) to investigate the corrosion due to activated colloidal crud. The Fickian diffusion model has been implemented as the reference corrosion model for the constituent component of the primary loop of the SMART reactor. The activated colloidal crud activity in the primary coolant and steam generator of the SMART reactor has been studied for different equilibrium corrosion rates, linear increase in corrosion rate, and dynamic RCP coastdown situation energy ratio b. The coolant specific activity of SMART reactor equilibrium corrosion (4.0 mg s1 ) has been found 9.63 103 mCi cm3 , 3.53 103 mC cm3 , 2.39 102 mC cm3 , 8.10 103 mC cm3 , 6.77 103 mC cm3 , 4.95 104 mC cm3 , 1.19 103 mC cm3 , and 7.87 104 mC cm3 for 24Na, 54Mn, 56Mn, 59Fe, 58Co, 60Co, 99Mo, and 51Cr which are 14.95%, 5.48%, 37.08%, 12.57%, 10.51%, 0.77%, 18.50%, and 0.12% respectively. For linear and exponential coastdown with a constant corrosion rate, the total coolant and steam generator activity approaches a higher saturation value than the normal values. The coolant and steam generator activity changes considerably with kinetic corrosion rate, equilibrium corrosion, growth of corrosion rate (DC/Dt), and RCP coastdown situations. The effect of the RCP coastdown on the specific activity of the steam generators is smeared by linearly rising corrosion rates, equilibrium corrosion, and rapid coasting down of the RCP. However, the time taken to reach the saturation activity is also influenced by the slope of corrosion rate, coastdown situation, equilibrium corrosion rate, and energy ratio b.

Abstract

The analysis of rapid flow transients in Reactor Coolant Pumps (RCP) is essential for a reactor safety study. An accurate and precise analysis of the RCP coastdown is necessary for the reactor design. The coastdown of RCP affects the coolant temperature and the colloidal crud in the primary coolant. A realistic and kinetic model has been used to investigate the behavior of activated colloidal crud in the primary coolant and steam generator that solves the pump speed analytically. The analytic solution of the non-dimensional flow rate has been determined by the energy ratio b. The kinetic energy of the coolant fluid and the kinetic energy stored in the rotating parts of a pump are two essential parameters in the form of b. Under normal operation, the pump's speed and moment of inertia are constant. However, in a coastdown situation, kinetic damping in the interval has been implemented. A dynamic model ACCP-SMART has been developed for System Integrated Modular and Advanced Reactor (SMART) to investigate the corrosion due to activated colloidal crud. The Fickian diffusion model has been implemented as the reference corrosion model for the constituent component of the primary loop of the SMART reactor. The activated colloidal crud activity in the primary coolant and steam generator of the SMART reactor has been studied for different equilibrium corrosion rates, linear increase in corrosion rate, and dynamic RCP coastdown situation energy ratio b. The coolant specific activity of SMART reactor equilibrium corrosion (4.0 mg s1 ) has been found 9.63 103 mCi cm3 , 3.53 103 mC cm3 , 2.39 102 mC cm3 , 8.10 103 mC cm3 , 6.77 103 mC cm3 , 4.95 104 mC cm3 , 1.19 103 mC cm3 , and 7.87 104 mC cm3 for 24Na, 54Mn, 56Mn, 59Fe, 58Co, 60Co, 99Mo, and 51Cr which are 14.95%, 5.48%, 37.08%, 12.57%, 10.51%, 0.77%, 18.50%, and 0.12% respectively. For linear and exponential coastdown with a constant corrosion rate, the total coolant and steam generator activity approaches a higher saturation value than the normal values. The coolant and steam generator activity changes considerably with kinetic corrosion rate, equilibrium corrosion, growth of corrosion rate (DC/Dt), and RCP coastdown situations. The effect of the RCP coastdown on the specific activity of the steam generators is smeared by linearly rising corrosion rates, equilibrium corrosion, and rapid coasting down of the RCP. However, the time taken to reach the saturation activity is also influenced by the slope of corrosion rate, coastdown situation, equilibrium corrosion rate, and energy ratio b.

참고문헌 (61)

  1. S. Wheatley, "Reassessing the safety of nuclear power", Energy Res. Social Sci, 15, pp.96~100 (2016)
  2. H. Gao, "Transient flow analysis in reactor coolant pump systems during flow coastdown period", Nucl. Eng. Des, 241, pp.509~514 (2011)
  3. J. Zhu, "Nuclear Reactor Safety Analysis" (2000), Xi'an Jiaotong University Press
  4. K. Natesan, "Significance of coastdown time on safety and availability of a pool type fast breeder reactor", Nucl. Eng. Des, 286, pp.77~88 (2015)
  5. Frederic Delabrouille, "Caracterisation par MET de fissures de corrosion sous contrainte d'alliages a base de nickel: influence de la teneur en chrome et de la chimie du milieu", PhD, pp.2004
  6. Primary Water Chemistry, Fuel Rod Corrosion, and Crud Deposition in PWRs: A Comparison of European and U.S. Plant Performance Crud Comparison, "EPRI", ~, pp.TR-107255 (1996)
  7. B. M. Caba~nas, "Sorption of nickel and cobalt ions onto cobalt and nickel ferrites", J. Colloid Interface Sci, 360, pp.695~700 (2011)
  8. B. M. Caba~nas, "Caba~nas, Comportement des produits de corrosion dans le circuit primaire des centrales REP - sorption du cobalt et du nickel sur des ferrites representatifs, Energie electrique", pp.2010
  9. Karl-Heinz Neeb, "Part 1, The Radiochemistry of Nuclear Power Plants with Light Water Reactors" (1997), Walter de Gruyter
  10. P. Belouschek, "Modelling of transport and deposition of corrosion production in primary circuits. In Water chemistry of nuclear reactor systems 7", Proceedings of the Conference Organized by the British Nuclear Energy Society and Held in Bournemouth (1996)
  11. P. De-Regge, "Radioactivity and Corrosion Product Concentration during the Normal Operation and Revision Shutdown of 900MWe PWR- Doel 3", 1988 JAIF International Conference on Water Chemistry in Nuclear Power Plants, Japan Atomic Industrial Forum, pp.175~181 (1988)
  12. P. Beslu, "Analyse hystorique" (2014), EDP Sciences
  13. J.M. Hawkes, "The simulation and study of conditions leading to axial Offset anomaly in pressurized water reactors", Doctor, pp.2004
  14. Mansour, "Sorption of sulfate ions onto magnetite", J. Colloid Interface Sci, 331, pp.77~82 (2009)
  15. "Modelisation des mecanismes de formation sous ebullition locale des dep^ots sur les gaines de combustible des reacteurs a eau sous pression conduisant a des activites volumiques importantes, in: Physique Nucleaire Experimentale, Universite de Strasbourg" (2013)[URL]
  16. Technical Report on the definition of primary coolant source terms used in the different EPR designs for shielding, radiation zoning, DBA consequences, "EPRI", Multinational Design Evaluation Programme, ~, pp.TR-EPRWG-03 (2015)
  17. A. Volborth, "Analytical Methods for Coal and Coal Products, vol. 3", pp.303~336 (1979)
  18. S.P. Murarka, "Neutron Activation Analysis, Encyclopaedia of Materials: Science and Technology", pp.1~5 (2001)
  19. Thermal Neutron Captures Cross Sections Resonance Integrals and G-Factors, Indc International Nuclear Data Committee, Indcnds -440, "S. F. Mughabghab", IAEA nuclear data section, ~ (2003)
  20. Reference neutron activation library, "IAEA", Nuclear Data Section International Atomic Energy Agency, ~, pp.IAEA-TECDOC-1285 (2002)
  21. Y. Alatrash, "Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor", Nucl. Eng. Des, 286, pp.60~66 (2015)
  22. Ji-WoongHan, "Investigation into the effects of a coastdown flow on the characteristics of early stage cooling of the reactor pool in KALIMER-600", Ann. Nucl. Energy, 36, pp.1325~1332 (2009)
  23. L. K. Chang, "The effect of primary pump coastdown characteristics on loss-of-flow transients without scram in EBR-II", Nucl. Eng. Des, 97(1), pp.49~59 (1986)
  24. Jianjun Zhou, "Three dimensional neutronic", thermal-hydraulic coupled simulation of MSR in transient state condition, 2015, pp.282(2), 93~105
  25. X. Liu, "Test study on safety features of station blackout accident for nuclear main pump", Atomic Energy Sci. Technol, 43, pp.448~451 (2009)
  26. M. Jiang, "Coast-down model based on rated parameters of reactor coolant pump", At. Energy Sci. Technol, 48, pp.1435~1439 (2014)
  27. Wu Guowei, "Primary pump coast-down characteristics analysis in lead cooled fast reactor under loss of flow transient", Ann. Nucl. Energy, 103, pp.1~9 (2017)
  28. Long Fei Zhang, "Influence of rotational inertia on transient performance of the main pump of marine nuclear power plant", Ship Ocean Eng, 2, pp.55~57 (2005)
  29. Q. Shi, "Study on the faults of nuclear power plant and effects on transient stability of power system", Electricity Distribution (CICED), 2012 China International Conference on, pp.1~ (2012), IEEE
  30. Yapei Zhang, "Transient analyses of station blackout accident for CPR1000", At. Energy Sci. Technol, 9, pp.1056~1059 (2011)
  31. N. M. Mirza, "Simulation of corrosion product activity for nonlinearly rising corrosion on inner surfaces of primary coolant pipes of a typical PWR under flow rate transients", Appl. Radiat. Isot, 62(5), pp.681~692 (2005)
  32. A. M. Mirza, "Simulation of corrosion product activity in pressurized water reactors under flow rate transients", Ann. Nucl. Energy, 25(6), pp.331~345 (1998)
  33. Paul K. Romano, "OpenMC : a state-of-the-art Monte Carlo code for research and development", Ann. Nucl. Energy, 82, pp.90~ (2015)[DOI]
  34. R. E. Melchers, "Predicting long-term corrosion of metal alloys in physical infrastructure", npj Mater Degrad, 3, pp.4~ (2019)[DOI]
  35. M. D. Carelli, "Handbook of Small Modular Nuclear Reactors" (2015)
  36. Basic Design Report of SMART, "M. H. Chang", Korea Atomic Energy Research Institute, ~, pp.KAERI (2002), TRe2142[DOI]
  37. K. Mehboob, "Derivation of radiological source term of Korean design system-integrated modular advanced ReacTor(SMART)", Ann. Nucl. Energy, 119, pp.148~161 (2018)
  38. In Kim Young, "CFD simulation for thermal mixing of a SMART flow mixing header assembly", Ann. Nucl. Energy, 85, pp.357~370 (2015)
  39. Al-Zahrani, "Analysis of Doppler reactivity coefficient in small modular reactor with UO2, MOX and (Th", U) O2 fuel, 2020, ~
  40. N. Dobuchi, "Study on the relation between Doppler reactivity coefficient and resonance integrals of Thorium and Uranium in PWR fuels", Ann. Nucl. Energy, 90, pp.191~194 (2016)
  41. Safety Analysis Report for SMART Basic Design, "S. H. Yang", Korea Atomic Energy Research Institute, ~, pp.KAERI (2002), TRe2173[DOI]
  42. "Status Report 77 e System-Integrated Modular Advanced Reactor (SMART) (IAEA)" (2011)[URL]
  43. "NNDCENDF/B-VII.1 evaluated nuclear data library" (2011)[URL]
  44. F. Deeba, "Modeling and simulation of corrosion product activity in pressurized water reactors under power perturbations", Ann. Nucl. Energy, 26(7), pp.561~578 (1999)
  45. Basic Design Report of SMART, "KAERI", Korea Atomic Energy Research Institute, ~, pp.KAERI (2002), TR-2142[DOI]
  46. Status of Small and Medium Sized Reactor Designs, A Supplement to the IAEA Advanced Reactors Information System (ARIS), "IAEA", International Atomic Energy Agency, ~ (2012)
  47. "Status Report 77 - System-Integrated Modular Advanced Reactor (SMART), Advanced Reactors Information System (ARIS)" (2011)[URL]
  48. E. Wylie, "Fluid Transients in Systems" (1993), Prentice-Hall
  49. M. Morcillo, "Atmospheric Corrosion", pp.195~214 (1995), American Society for Testing and Materials
  50. J. Tidblad, "Marine corrosion in tropical environments, STP 1399", Am. Soc. for Testing and Materials, 18-32, pp.18~32 (2000)
  51. D. De la Fuente, "Studies of long-term weathering of aluminium in the atmosphere", Corrosion Sci, 49, pp.3134~3148 (2007)
  52. J. Alcantara, "Marine atmospheric corrosion of carbon steel : a review", Materials, 4(10), pp.406~ (2017)[DOI]
  53. R. G. Jaeger, "Engineering Compendium on Radiation Shielding, vol. III" (1970), Springer-Verlag
  54. WEC, "The Westinghouse Pressurized Water Reactor Nuclear Power Plant", Document Number 6863.Doc-8, 2005 Westinghouse Electric Corporation, Water Reactor Divisions Pittsburgh, pp.2005, ~
  55. Q. Guo, "Develop CATE V3.0 code for multi-phase ACPs analysis in a typical PWR", Ann. Nucl. Energy, 141, pp.107345~ (2020)
  56. Rafique, "Kinetic study of corrosion product activity in primary coolant pipes of a typical PWR under flow rate transients and linearly increasing corrosion rates", J. Nucl. Mater, 346, pp.282~292 (2005)
  57. F. Mehmood, "Dynamic response analysis of corrosion products activity under steady state operation and Mechanical Shim based powermaneuvering transients in AP-1000", Ann. Nucl. Energy, 115, pp.16~26 (2018)
  58. N. M. Mirza, "Computer simulation of corrosion product activity in primary coolants of a typical PWR under flow rate transients and linearly accelerating corrosion", Ann. Nucl. Energy, 30, pp.831~851 (2003)
  59. R. Nasir, "Evaluation of corrosion product activity in a typical PWR with extended cycles and flow rate perturbations", World J. Nucl. Sci. Technol, 7, pp.24~34 (2017)
  60. M. Rafique, "Parametric study of time-dependent corrosion product activity due to 56Mn, 58Co, and 60Co in the primary coolant circuit of a typical pressurized water reactor", J. Chem, 2015, pp.1~10 (2015)[DOI]
  61. Corrosion Products Transport in PWRS Primary Circuit- Computer Code CPPWR. ÚJV 9223 T, "M. Zmítke", Nuclear Research Institute REZ e Czechoslovakia, ~ (1990)

관련 논문AI추천

이 간행물의 다른 논문 (39건)