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Assessment of Mass Fraction and Melting Temperature for the Application of Limestone Concrete and Siliceous Concrete to Nuclear Reactor Basemat Considering Molten Coree-Concrete Interaction

  • Lee, Hojae (Korea Institute of Civil Engineering & Building Technology) ;
  • Cho, Jae-Leon (Korea Hydro & Nuclear Power Co.) ;
  • Yoon, Eui-Sik (Korea Institute of Nuclear Safety) ;
  • Cho, Myungsug (Korea Hydro & Nuclear Power Co., Central Research Institute) ;
  • Kim, Do-Gyeum (Korea Institute of Civil Engineering & Building Technology)
  • Received : 2015.03.06
  • Accepted : 2015.12.30
  • Published : 2016.04.25

Abstract

Severe accident scenarios in nuclear reactors, such as nuclear meltdown, reveal that an extremely hot molten core may fall into the nuclear reactor cavity and seriously affect the safety of the nuclear containment vessel due to the chain reaction caused by the reaction between the molten core and concrete. This paper reports on research focused on the type and amount of vapor produced during the reaction between a high-temperature molten core and concrete, as well as on the erosion rate of concrete and the heat transfer characteristics at its vicinity. This study identifies themass fraction and melting temperature as the most influential properties of concrete necessary for a safety analysis conducted in relation to the thermal interaction between the molten core and the basemat concrete. The types of concrete that are actually used in nuclear reactor cavities were investigated. The $H_2O$ content in concrete required for the computation of the relative amount of gases generated by the chemical reaction of the vapor, the quantity of $CO_2$ necessary for computing the cooling speed of the molten core, and the melting temperature of concrete are evaluated experimentally for the molten core-concrete interaction analysis.

Keywords

References

  1. M.T. Farmer, B.W. Spencer, B.R. Seghal, MACE Core Coolability Test M1B, 20th Water Reactor Safety Meeting, Bethesda, MD, 1992.
  2. R.E. Blose, J.E. Gronager, A.J. Suo-Anttila, J.E. Brockmann, SWISS: sustained heated metallic melt/concrete interactions with overlying water pools, NUREG/CR4727, SANDS85-1546 R#, R4, R7, 1987.
  3. CORCON-MOD3: An Assessment of the CORCON-MOD3 Code Part I: Thermal-Hydraulic Calculations, International Agreement Report, NUREG/IA-0129 Part I, U.S. Nuclear Regulatory Commission.
  4. CORCON-MOD3: An Integrated Computer Model for Analysis of Molten CoreeConcrete Interactions User's Manual, NUREG/CR-5843 SAND92-0167, U.S. Nuclear Regulatory Commission.
  5. ASTM C 1084. Standard Test Method for Portland-Cement Content of Hardened Hydraulic-Cement Concrete.
  6. ISO 3082. Iron Ores-Sampling and Sample Preparation Procedures.
  7. KS E 3605. Particulate Materials-General Rules for Methods of Sampling.
  8. ASTM C 642. Standard Test Method for Density, Absorption, and Voids in Hardened Concrete.
  9. KS M ISO 11358. Plastics-Thermogravimetry (TG) of Polymers-General principles.
  10. H.J. Lee, J.H. Lee, M.S. Cho, D.G. Kim, Analysis of Carbonation Properties of NPP Concrete Using Thermogravimetric and X-ray Diffraction Method, Vol. 24, No. 1, Korea Institute of Concrete, 2012.
  11. S.G. Park, Principal and usage of TG-DTA, Cement 65 (1976) 25-31.
  12. S.H. Park, A Comparative Study on Analyzing Methods for Improving the Efficiency of the Heavy Metal Exposure Assessment, Occupational Safety and Health Research Institute, 2000.
  13. KS E ISO 9516-1. Iron Ores-Determination of Various Elements by X-Ray Fluorescence Spectrometry-Part 1: Comprehensive procedure.
  14. KS D 0069. Method of Determining the Crystallization Temperatures of Amorphous Metals.
  15. KS M ISO 11357-3. Plastics-Differential Scanning Calorimetry (DSC)-Part 3.