한국압력기기공학회 논문집 (Transactions of the Korean Society of Pressure Vessels and Piping)

한국압력기기공학회 (Korean Society of Pressure Vessels and Piping)
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UNIST-DISNY 설비 피복관에 침적된 크러드의 열전달 모델링

Modelling Heat Transfer Through CRUD Deposited on Cladding Tube in UNIST-DISNY Facility

  • Seon Oh YU (Korea Institute of Nuclear Safety, Univ. of Science and Technology) ;
  • Ji Yong Kim (Ulsan National Institute of Science and Technology) ;
  • In Cheol Bang (Ulsan National Institute of Science and Technology)
  • 투고 : 2023.11.09
  • 심사 : 2023.12.15
  • 발행 : 2023.12.30
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초록

This study presents a CRUD modelling to simulate the thermal resistance behavior of CRUD, deposited on the surface of a cladding tube of a fuel assembly. When heat produced from fuels transfers to a coolant through a cladding tube, the CRUD acting as an additional thermal resistance is expressed as two layers, i.e., a solid oxide layer and an imaginary fluid layer, which are added to the experimental tube's heat structure of the MARS-KS input data. The validation calculation for the experiments performed in UNIST-DISNY facility showed that the center and surface temperatures of the cladding tube increased as the porosity and the steam amount inside pores of the CRUD got higher. In addition, the temperature gradient in the imaginary fluid layer was calculated to be larger than that in the solid oxide part, indicating that the steam amount inside the layer acted more largely as thermal resistance. It was also evaluated through sensitivity calculations that the cladding tube temperature was more sensitive to the CRUD porosity and the steam amount in pores than to the inlet flow rate of the coolant.

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과제정보

본 연구는 원자력안전위원회의 재원으로 한국원자력안전재단의 지원을 받아 수행한 원자력안전연구 원자력안전규제기술개발 사업의 연구결과입니다(No. 2106022).

참고문헌

  1. Deshon, J., 2006, "Evaluation of Fuel Cladding Corrosion and Corrosion Product Deposits from Callaway Cycle 14," Electric Power Research Institute, Palo Alto, CA, 1013425.
  2. Deshon, J., 2011, "Simulated Fuel Crud Thermal Conductivity Measurements Under Pressurized Water Reactor Conditions," Electric Power Research Institute, Palo Alto, CA, 1022896.
  3. Yeon, J. W., Choi, I. K., Park, K. K., Kwon, H. M., and Song, K., 2010, "Chemical Analysis of Fuel CRUD Obtained from Korean Nuclear Power Plants," J NUCL MATER, Vol. 404, No. 2, pp. 160-164. doi:https://doi.org/10.1016/j.jnucmat.2010.07.024
  4. Hu, R., Kazimi, M. S., and Leyse, M. E., 2009, "Considering the Thermal Resistance of CRUD in LOCA Analysis," T AM NUCL SOC, Vol. 101, pp. 590-592.
  5. Yeo, D. and NO, H., 2017, "Modeling Heat Transfer Through Chimney-Structured Porous Deposit Formed in Pressurized Water Reactors," INT J HEAT MASS TRAN, Vol. 108, pp. 868-879. doi:https://doi.org/10.1016/j.ijheatmasstransfer.2016.12.046
  6. Lee, J., Jeong, H., and Bang, Y., 2018, "Thermal Resistance Effects of CRUD and Oxide Layers to the Safety Analysis," Proc. Of Annual Topical Meeting on Reactor Fuel Performance, Prague, Czech Republic.
  7. Dumnernchanvanit, I., Zhang, N. Q., Robertson, S., Delmore, A., Carlson, M. B., Hussey, D., and Short, M. P., 2018, "Initial Experimental Evaluation of CRUD-resistant Materials for Light Water Reactors," J NUCL MATER, Vol. 498, pp. 1-8. doi:https://doi.org/10.1016/j.jnucmat.2017.10.010
  8. Baek, S. H., Shim, H. S., Kim, J. G., and Hur, D.H., 2018, "Effect of Chemical Etching of Fuel Cladding Surface on CRUD Deposition Behavior in Simulated Primary Water of PWRs at 328 ℃," ANN NUCL ENERGY, Vol. 116, pp. 69-77. doi:https://doi.org/10.1016/j.anucene.2018.02.030
  9. Baek, S. H., Shim, H. S., Kim, J. G., and Hur, D. H., 2019, "Effects of Heat Flux on Fuel CRUD Deposition and Sub-cooled Nucleate Boiling in Simulated PWR Primary Water at 13  MPa," ANN NUCL ENERGY, Vol. 133, pp. 178-185. doi:https://doi.org/10.1016/j.anucene.2019.05.022
  10. Kim, J. Y., Lee, Y., Kim, J., and Bang, I. C., 2022, "The DISNY Facility for Sub-cooled Flow Boiling Performance Analysis of CRUD Deposited Zirconium Alloy Cladding Under Pressurized Water Reactor Condition: Design, construction, and opeartion," NUCL ENG TECHNOL, Vol. 55, No. 9, pp. 3164-3182. doi:https://doi.org/10.1016/j.net.2023.06.006
  11. KINS, 2021, "MARS-KS Code Manual," Korea Institute of Nuclear Safety, Daejeon, KINS/RR-1822.
  12. Kingery, W. D., Francl, J., Coble, R. L., and Vasilos, T., 1954, "Thermal Conductivity: X, Data for Several Pure Oxide Materials Corrected to Zero Porosity," J AM CERAM SOC, Vol. 37, No. 2, pp. 107-111. https://doi.org/10.1111/j.1551-2916.1954.tb20109.x
  13. Nelson, A. T., White, J. T., Anderson, D. A., Aguiar, J. A., McClellan, K. J., Byler, D. D., Short, M. P., and Stanek, C. R., 2014, "Thermal Expansion, Heat Capacity and Thermal Conductivity of Nickel Ferrite (NiFe2O4)," J AM CERAM SOC, Vol. 97, No. 5, pp. 1559-1565. doi:https://doi.org/10.1111/jace.12901
  14. Noda, Y. and Naito, K., 1978, "The Thermal Conductivity and Diffusivity of MnxFe3-xO4 (0≤x≤1.5) from 200 to 700K," NETSUSOKUTEI, Vol. 5, No. 1, pp. 11-18.
  15. Prostakova, V., Chen, J., Jak, E., and Decterov, S.A., 2012, "Experimental Study and Thermodynamic Optimization of the CaO-NiO, MgO-NiO and NiO-SiO2 Systems," Computer Coupling of Phase Diagrams and Thermochemistry, Vol. 37, pp. 1-10. doi:https://doi.org/10.1016/j.calphad.2011.12.009
  16. NIST Chemistry WebBook, 2023, "https://webbook.nist.gov/", Chemistry WebBook, SRD 69.