Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

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

  • Khurram Mehboob (Department of Nuclear Engineering, College of Engineering, King Abdulaziz University) ;
  • Yahya A. Al-Zahrani (Department of Nuclear Engineering, College of Engineering, King Abdulaziz University)
  • Received : 2022.02.01
  • Accepted : 2022.08.16
  • Published : 2022.12.25
Download PDF
⟨ Previous Next ⟩

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 β. 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 β. 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 s-1) has been found 9.63×10-3 µCi cm-3, 3.53×10-3 µC cm-3, 2.39×10-2 µC cm-3, 8.10×10-3 µC cm-3, 6.77× 10-3 µC cm-3, 4.95×10-4 µC cm-3, 1.19×10-3 µC cm-3, and 7.87×10-4 µC cm-3 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 (ΔC/Δt), 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 β.

Keywords

Acknowledgement

The authors acknowledge the support provided by King Abdullah City for Atomic and Renewable Energy (K.A. CARE) under K.A. CAREKing Abdulaziz University Collaboration Program. The authors extend their appreciation to the Deputyship for Research & Innovation, Ministry of Education in Saudi Arabia for funding this research work through the project number "IFPHI-331-135-2020" and King Abdulaziz University DSR, Jeddah, Saudi Arabia.

References

  1. S. Wheatley, B.K. Sovacool, D. Sornette, Reassessing the safety of nuclear power, Energy Res. Social Sci. 15 (2016) 96-100. https://doi.org/10.1016/j.erss.2015.12.026
  2. H. Gao, et al., Transient flow analysis in reactor coolant pump systems during flow coastdown period, Nucl. Eng. Des. 241 (2011) 509-514. https://doi.org/10.1016/j.nucengdes.2010.09.033
  3. J. Zhu, Nuclear Reactor Safety Analysis, Xi'an Jiaotong University Press, 2000.
  4. K. Natesan, et al., Significance of coastdown time on safety and availability of a pool type fast breeder reactor, Nucl. Eng. Des. 286 (2015) 77-88. https://doi.org/10.1016/j.nucengdes.2015.01.021
  5. Frederic Delabrouille, Caracterisation par MET defissures de corrosion sous contrainte d'alliages a base de nickel: influence de la teneur en chrome et de la chimie du milieu, PhD, Institut National Polytechnique de Toulouse, 2004 (PhD Thesis).
  6. EPRI, Primary Water Chemistry, Fuel Rod Corrosion, and Crud Deposition in PWRs: A Comparison of European and U.S. Plant Performance Crud Comparison, TR-107255, 1996.
  7. B.M. Cabanas, Sorption of nickel and cobalt ions onto cobalt and nickel ferrites, J. Colloid Interface Sci. 360 (2011) 695-700. https://doi.org/10.1016/j.jcis.2011.04.082
  8. B.M. Cabanas, Comportement des produits de corrosion dans le circuit primaire des centrales REP - sorption du cobalt et du nickel sur des ferrites representatifs, Energieelectrique. Universite Paris Sud - Paris XI (2010). Francais. , 2011.
  9. Karl-Heinz Neeb, Part 1, The Radiochemistry of Nuclear Power Plants with Light Water Reactors, Walter de Gruyter.Berlin., New York, 1997, ISBN 3-11-013242-7.
  10. P. Belouschek, et al., Modelling of transport and deposition of corrosion production in primary circuits. In Water chemistry of nuclear reactor systems 7, in: Proceedings of the Conference Organized by the British Nuclear Energy Society and Held in Bournemouth, 1996 on October 13-17.
  11. P. De-Regge, K. Dinov, K. De Ranter, Radioactivity and Corrosion Product Concentration during the Normal Operation and Revision Shutdown of 900 MWe PWR- Doel 3, 1988 JAIF International Conference on Water Chemistry in Nuclear Power Plants, Japan Atomic Industrial Forum, Tokyo, 1988, pp. 175-181.
  12. P. Beslu, Corrosion des circuits primaires dans les reacteurs a eau sous pression, Analyse hystorique, 2014. EDP Sciences.
  13. J.M. Hawkes, The simulation and study of conditions leading to axial Offset anomaly in pressurized water reactors, Doctoral Thesis (2004). Georgia Institute of Technology.
  14. Mansour, et al., Sorption of sulfate ions onto magnetite, J. Colloid Interface Sci. 331 (2009) 77-82. https://doi.org/10.1016/j.jcis.2008.11.009
  15. A. Ferrer, Modelisation des mecanismes de formation sousebullition locale des depots sur les gaines de combustible des reacteursa eau sous pression conduisant a des activites volumiques importantes, in: Physique Nucleaire Experimentale, Universite de Strasbourg, 2013. Francais, http://www.theses.fr/2013STRAE040/document.
  16. EPRI, Technical Report on the definition of primary coolant source terms used in the different EPR designs for shielding, radiation zoning, DBA consequences, in: Multinational Design Evaluation Programme, 2015. TR-EPRWG-03 - PUBLIC USE. Technical report, TR-EPRWG-03. Evolutionary Power Reactor.
  17. A. Volborth, Chapter 47 - Fast-Neutron Activation Analysis for Oxygen, Nitrogen, and Silicon in Coal, Coal Ash, and Related Products in Analytical Methods for Coal and Coal Products, vol. 3, 1979, pp. 303-336, 1979. https://doi.org/10.1016/B978-0-12-399903-0.50016-7
  18. S.P. Murarka, Neutron Activation Analysis, Encyclopaedia of Materials: Science and Technology, second ed., 2001, pp. 1-5.
  19. S.F. Mughabghab, Thermal Neutron Captures Cross Sections Resonance Integrals and G-Factors, Indc International Nuclear Data Committee, Indcnds-440, IAEA nuclear data section, Vienna, Austria, 2003.
  20. IAEA, Reference neutron activation library, IAEA-TECDOC-1285, Nuclear Data Section International Atomic Energy Agency, Vienna, Austria, 2002.
  21. Y. Alatrash, et al., Experimental and analytical investigations of primary coolant pump coastdown phenomena for the Jordan Research and Training Reactor, Nucl. Eng. Des. 286 (2015) 60-66. https://doi.org/10.1016/j.nucengdes.2015.01.018
  22. Ji-WoongHan, et al., 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 (2009) 1325-1332. https://doi.org/10.1016/j.anucene.2009.07.004
  23. L.K. Chang, D. Mohr, The effect of primary pump coastdown characteristics on loss-of-flow transients without scram in EBR-II, Nucl. Eng. Des. 97 (1) (1986) 49-59. https://doi.org/10.1016/0029-5493(86)90070-1
  24. Jianjun Zhou, et al., Three dimensional neutronic/thermal-hydraulic coupled simulation of MSR in transient state condition, Nucl. Eng. Des. 282 (2) (2015) 93-105. https://doi.org/10.1016/j.nucengdes.2014.11.026
  25. X. Liu, J. Liu, D. Wang, et al., Test study on safety features of station blackout accident for nuclear main pump, Atomic Energy Sci. Technol. 43 (2009) 448-451.
  26. M. Jiang, et al., Coast-down model based on rated parameters of reactor coolant pump, At. Energy Sci. Technol. 48 (2014) 1435-1439.
  27. Wu Guowei, et al., Primary pump coast-down characteristics analysis in lead cooled fast reactor under loss of flow transient, Ann. Nucl. Energy 103 (2017) 1-9. https://doi.org/10.1016/j.anucene.2016.11.023
  28. Long Fei Zhang, Dafa Zhang, Shaoming Wang, Influence of rotational inertia on transient performance of the main pump of marine nuclear power plant, Ship Ocean Eng 2 (2005) 55-57.
  29. Q. Shi, D. Liu, H. Luo, et al., Study on the faults of nuclear power plant and effects on transient stability of power system, in: Electricity Distribution (CICED), 2012 China International Conference on, IEEE, 2012, p. 1. -5.
  30. Yapei Zhang, Wenxi Tian, Sui Zheng Qiu, Guanghui Su, Transient analyses of station blackout accident for CPR1000, At. Energy Sci. Technol. 9 (2011) 1056-1059.
  31. N.M. Mirza, et al., 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) (2005) 681-692. https://doi.org/10.1016/j.apradiso.2004.12.005
  32. A.M. Mirza, et al., Simulation of corrosion product activity in pressurized water reactors under flow rate transients, Ann. Nucl. Energy 25 (6) (1998) 331-345. https://doi.org/10.1016/S0306-4549(97)00062-5
  33. Paul K. Romano, Nicholas E. Horelik, Bryan R. Herman, Adam G. Nelson, Benoit forget, and kord smith, OpenMC: a state-of-the-art Monte Carlo code for research and development, Ann. Nucl. Energy 82 (2015) 90-97. https://doi.org/10.1016/j.anucene.2014.07.048
  34. R.E. Melchers, Predicting long-term corrosion of metal alloys in physical infrastructure, npj Mater Degrad 3 (2019) 4, https://doi.org/10.1038/s41529-018-0066-x.
  35. M.D. Carelli, D.T. Ingersoll, Handbook of Small Modular Nuclear Reactors, Woodhead Publishing Series in Energy Number 64, 2015.
  36. M.H. Chang, et al., Basic Design Report of SMART". KAERI/TR-2142/2002, Korea Atomic Energy Research Institute, 2002.
  37. K. Mehboob, Aljohani, Derivation of radiological source term of Korean design system-integrated modular advanced ReacTor (SMART), Ann. Nucl. Energy 119 (2018) 148-161. https://doi.org/10.1016/j.anucene.2018.04.044
  38. In Kim Young, et al., CFD simulation for thermal mixing of a SMART flow mixing header assembly, Ann. Nucl. Energy 85 (2015) 357-370. https://doi.org/10.1016/j.anucene.2015.05.019
  39. Al-Zahrani, et al., Analysis of Doppler reactivity coefficient in small modular reactor with UO2, MOX and (Th/U) O2 fuel. Proceedings of 2020 28th International Conference on Nuclear Engineering Joint with the ASME 2020 Power Conference ICONE28-Power2020 August 2-6, 2020, Anaheim, California, USA. (Accepted for publication).
  40. N. Dobuchi, S. Takeda, T. Kitada, Study on the relation between Doppler reactivity coefficient and resonance integrals of Thorium and Uranium in PWR fuels, Ann. Nucl. Energy 90 (2016) 191e194.
  41. S.H. Yang, et al., Safety Analysis Report for SMART Basic Design" KAERI/TR-2173/2002, Korea Atomic Energy Research Institute, 2002.
  42. Advanced Reactor Information System, Status Report 77 - System-Integrated Modular Advanced Reactor (SMART) (IAEA), Vienna, Austria, international Atomic Energy Agency, 2011. Available, https://aris.iaea.org/PDF/SMART.pdf.
  43. NNDC, NNDCENDF/B-VII.1 evaluated nuclear data library. https://www.nndc.bnl.gov/endf/b7.1/aceFiles/ENDF-B-VII.1-neutron-293.6K.tar.gzGoogleScholar, 2011.
  44. F. Deeba, A.M. Mirza, N.M. Mirza, Modeling and simulation of corrosion product activity in pressurized water reactors under power perturbations, Ann. Nucl. Energy 26 (7) (1999) 561-578. https://doi.org/10.1016/S0306-4549(98)00087-5
  45. KAERI, Basic Design Report of SMART, KAERI/TR-2142/2002, Korea Atomic Energy Research Institute, Taejon (Korea, Republic of), 2002.
  46. IAEA, Status of Small and Medium Sized Reactor Designs, A Supplement to the IAEA Advanced Reactors Information System (ARIS), International Atomic Energy Agency, Vienna, Austria, 2012.
  47. ARIS, Status Report 77 - System-Integrated Modular Advanced Reactor (SMART), Advanced Reactors Information System (ARIS), IAEA, International Atomic Energy Agency, Vienna, Austria, 2011. URL: https://aris.iaea.org/pdf/SMART.pdf.
  48. E. Wylie, V. Streeter, Fluid Transients in Systems, Prentice-Hall, Englewood Cliffs, NJ, 1993.
  49. M. Morcillo, J. Simancas, S. Feliu, 195-214, in: W.W. Kirk, H.H. Lawson (Eds.), Atmospheric Corrosion, ASTM STP 1239, American Society for Testing and Materials, Philadelphia, 1995, 1995.
  50. J. Tidblad, A.A. Mikailov, V. Kucera, Marine corrosion in tropical environments, STP 1399, Am. Soc. for Testing and Materials, in: S.W. Dean, H.-D. Delgadillo, J.B. Bushman (Eds.), West Conshohocken, vols. 18-32, 2000, 2000.
  51. D. De la Fuente, E. Otero-Huerta, M. Morcillo, Studies of long-term weathering of aluminium in the atmosphere, Corrosion Sci. 49 (2007) 3134-3148. https://doi.org/10.1016/j.corsci.2007.01.006
  52. J. Alcantara, et al., Marine atmospheric corrosion of carbon steel: a review, Materials 4 (10) (2017) 406, https://doi.org/10.3390/ma10040406.
  53. R.G. Jaeger, Engineering Compendium on Radiation Shielding, vol. III, Springer-Verlag, New York, 1970.
  54. WEC, The Westinghouse Pressurized Water Reactor Nuclear Power Plant. Document Number 6863.Doc-8/11/2005 Westinghouse Electric Corporation, Water Reactor Divisions Pittsburgh, Pennsylvania, 2005.
  55. Q. Guo, et al., Develop CATE V3.0 code for multi-phase ACPs analysis in a typical PWR, Ann. Nucl. Energy 141 (2020), 107345.
  56. Rafique, et al., 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 (2005) 282-292. https://doi.org/10.1016/j.jnucmat.2005.07.002
  57. F. Mehmood, et al., Dynamic response analysis of corrosion products activity under steady state operation and Mechanical Shim based power-maneuvering transients in AP-1000, Ann. Nucl. Energy 115 (2018) 16-26. https://doi.org/10.1016/j.anucene.2018.01.009
  58. N.M. Mirza, et al., 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 (2003) 831-851. https://doi.org/10.1016/S0306-4549(02)00142-1
  59. R. Nasir, et al., Evaluation of corrosion product activity in a typical PWR with extended cycles and flow rate perturbations, World J. Nucl. Sci. Technol. 7 (2017) 24-34. https://doi.org/10.4236/wjnst.2017.71003
  60. M. Rafique, et al., 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 (2015) 1-10, https://doi.org/10.1155/2015/809672, 809672.
  61. M. Zmitke, Corrosion Products Transport in PWRS Primary Circuit- Computer Code CPPWR. UJV 9223 T, Nuclear Research Institute REZ - Czechoslovakia, 1990.