Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT) (방사성폐기물학회지)

Korean Radioactive Waste Society (한국방사성폐기물학회)
권호 표지
DOI QR코드

DOI QR Code

State-of-Arts of Primary Concrete Degradation Behaviors due to High Temperature and Radiation in Spent Fuel Dry Storage

사용후핵연료 건식저장 콘크리트의 고열과 방사선으로 인한 주요 열화거동 분석

  • Received : 2017.12.20
  • Accepted : 2018.05.18
  • Published : 2018.06.29
Download PDF
⟨ Previous Next ⟩

Abstract

A literature review on the effects of high temperature and radiation on radiation shielding concrete in Spent Fuel Dry Storage is presented in this study with a focus on concrete degradation. The general threshold is $95^{\circ}C$ for preventing long-term degradation from high temperature, and it is suggested that the temperature gradient should be less than $60^{\circ}C$ to avoid crack generation in concrete structures. The amount of damage depends on the characteristics of the concrete mixture, and increases with the temperature and exposure time. The tensile strength of concrete is more susceptible than the compressive strength to degradation due to high temperature. Nuclear heating from radiation can be neglected under an incident energy flux density of $10^{10}MeV{\cdot}cm^{-2}{\cdot}s^{-1}$. Neutron radiation of >$10^{19}n{\cdot}cm^{-2}$ or an integrated dose of gamma radiation exceeding $10^{10}$ rads can cause a reduction in the compressive and tensile strengths and the elastic moduli. When concrete is highly irradiated, changes in the mechanical properties are primarily caused by variation in water content resulting from high temperature, volume expansion, and crack generation. It is necessary to fully utilize previous research for effective technology development and licensing of a Korean dry storage system. This study can serve as important baseline data for developing domestic technology with regard to concrete casks of an SF (Spent Fuel) dry storage system.

사용후핵연료 건식저장 시스템과 관련하여 고온 및 방사선으로 인한 콘크리트 손상과 열화특성에 대해 포괄적으로 문헌분석을 수행하였다. 고온에 의한 장기열화를 방지하기 위한 콘크리트의 임계온도는 일반적으로 $95^{\circ}C$이며, 온도경사는 콘크리트 균열방지를 위해 $60^{\circ}C$ 이하가 되도록 설정하고 있다. 열화정도는 노출온도와 노출시간에 비례하여 증가하는 경향을 나타내며, 압축강도에 비해 인장강도가 고온에 보다 민감한 특성을 보인다. 한편 방사선의 에너지가 $10^{10}MeV{\cdot}cm^{-2}{\cdot}s^{-1}$ 이하일 경우에는 핵반응으로 인한 가열을 무시할 수 있다. 하지만 콘크리트가 $10^{19}n{\cdot}cm^{-2}$ 이상의 중성자에 혹은 $10^{10}$ rad를 초과하는 감마선량에 노출된다면 콘크리트의 역학적 물성이 점차 감소하는 경향을 보이며, 그 손상정도는 콘크리트 구성재료의 특성에 의존적이다. 콘크리트에 대한 방사선 조사시 재료의 역학적 물성변화는 주로 온도상승으로 인한 콘크리트 내부 함수량의 변화 및 재료간의 열적물성 차이로 인한 체적증가와 균열발생으로 발생한다. 따라서 건식저장과 관련된 기술의 조속한 확보 및 인 허가를 위해서는 그 간의 선행연구 결과를 최대한 활용할 필요가 있으며, 본 연구결과는 향후 사용후핵연료 건식저장 콘크리트 캐스크 관련 국내 자체기술 개발에 중요한 기초자료로 활용될 수 있을 것이다.

Keywords

References

  1. J.W. Choi, J.N. Chang, W.S. Ryu, G.W. Song, J.G. Bang, et al., "Development of Integrity Evaluation Technology for the Long-term Spent Fuel Dry Storage System", Korea Atomic Energy Research Institute Report, KAERI/RR-3157/2009 (2009).
  2. J.S. Kim, J.W. Choi, K.S. Lee, and S. Kwon, "The state of the Technology: Radiation Damage and Deterioration of Concrete Cask in Spent Fuel Dry Storage System", Korea Atomic Energy Research Institute Report, KAERI/AR/851/2010 (2010).
  3. J.S. Kim, K.S. Lee, J.W. Choi, and S. Kwon, "A Literature Review: The effect of Thermal Damage on Ther Physical and Mechanical Properties of Concrete Materials", Korea Atomic Energy Research Institute Report, KAERI/AR-876/2011 (2011).
  4. H. Issard, F. Nizeyimana, E. Cavaletti, and J. Garcia, "Managing Degradation of Materials in Used Nuclear Fuel Dry Storage", IAEA TM 45455, Used Fuel Storage Options, July, 2-4, Vienna (2013).
  5. A.H. Chowdhury, L. Caseres, Y.M. Pan, G. Oberson, and C. Jones, Expert panel workshop on concrete degradation in spent nuclear fuel dry cask storage systems-Summary report, US. NRC (2016).
  6. J.S. Kim, S.W. Cha, and J.W. Choi, "The State of Primary Degradation Models of Concrete Structure and Development of the Optimized Degradation Model", Korea Atomic Energy Research Institute Report, KAERI/TR-4303/2011 (2011).
  7. F.P. Glasser, J. Marchand, and E. Samson, "Durability of Concrete-Degradation Phenomena involving Detrimental Chemical Reactions", Cement and Concrete Research, 38, 226-246 (2008). https://doi.org/10.1016/j.cemconres.2007.09.015
  8. M.F. Kaplan, "Concrete Radiation Shielding_Nuclear Physics, Concrete Properties, Design and Construction", John Wiley & Sons, INC., New York (1989).
  9. H.E. Hungerford, "Shielding in fast reactor technology: plant design", Yevick, J.G., (ed.), MIT Press, Ch.8 (1966).
  10. R.G. Jaeger,(ed.), "Engineering compendium on radiation shielding, Vol. II: shielding materials", S.9.1.12.5. Springer-Verlag, Berlin, Heidelberg, New York (1975).
  11. E.G. Peterson, "Shielding Properties of Ordinary Concrete as a Function Temperature", USAEC Report HW-65572 (1960).
  12. B.T. Price, C.C. Horton, and K.T. Spinney, "Radiation Shielding", Pergamon Press, London (1957).
  13. H. Goldstein, Fundamental aspects of reactor shielding. Addison-Wesley, Cambridge, USA (1959).
  14. K. Billig, "Prestressed concrete pressure vessels", J. Amer. Concr. Inst., 59(11), 1601-1634 (1962).
  15. J.S. Davis, "High-density concrete for shielding atomic energy plants", J. Amer. Concr. Inst., 29(11) (1958).
  16. T. Rockwell (ed.), "Reactor Shielding Design Manual", McGraw-Hill, New York (1956).
  17. U. Schneider, "Behaviour of Concrete at High Temperature", Deutscher Ausschuss Fur Stahlbeton, Heft 337, Berlin (1982).
  18. Y. Anderberg and S. Thelanderson, "Stress and Deformation Characteristics of Concrete at High Temperatures, 2-Experimental Investigation and Material Behaviour Model", Bulletin 54, Lund Institute of Technology, Lund, Sweden (1976).
  19. T. Blundell, C. Dimond, and R.G. Browne, "The Properties of Concrete subjected to Elevated Temperatures", CIRIA Underwater Engineering Group, Technical Note No. 9, London (1976).
  20. E. Crispino, "Studies on the Technology of Concretes under Thermal Conditions", CIRIA Underwater Engineering Group. Paper SP34-25, Vol. I, 443-479 (1972).
  21. R. Blundell, "Session VII discussions on Structure, Solid Mechanics and Engineering Design", Proc. Conf. on Civil Engineering Materials, Southampton (1969).
  22. T. Harada, J. Takeda, S. Yamane, and F. Furumura, "Strength, elasticity and thermal properties of concrete subjected to elevated temperatures", CIRIA Underwater Engineering Group. Paper SP34-21, Vol. I, 377-406 (1972).
  23. U. Diederishs and U. Schneider, "Bond strength at high temperatures", Magazine of Concrete Research. 33(115), 75-84 (1981). https://doi.org/10.1680/macr.1981.33.115.75
  24. K. Hertz, "The anchorage capacity of reinforcing bars at normal and high temperatures", Magazine of Concrete Research, 34(121), 213-220 (1972). https://doi.org/10.1680/macr.1982.34.121.213
  25. T. Harada, "Variations of Thermal Conductivity of Cement Mortars and Concrete under High Temperatures", Trans. Architectural Institute of Japan, No.49, Tokyo (1954).
  26. J.C. Marechal, "Thermal Conductivity and Thermal Expansion Coefficients of Concrete as a Function of Temperature and Humidity", CIRIA Underwater Engineering Group. Paper SP34-49, Vol. II, 1047-1057 (1972).
  27. H.S. Davis, "Effects of High-Temperature Exposure on Concrete", Materials Research and Standards, 7(10), 452-459 (1967).
  28. H. Weigler and R. Fishcer, "Influence of High Temperatures on Strength and Deformations of Concrete", Amer. Concr. Inst. Special Publication SP-34: Concrete for Nuclear Reactors. Paper SP34-26, Vol. I, 481-493 (1972).
  29. R. Idine, J. Lee, and B. Bresler, "Behaviour of Reinforced Concrete under Variable Elevated Temperatures", University of California Fire Research Group Report No. UCB.FRG 75-8 (1975).
  30. S. Ohgishi, S. Miyasaka, and J. Chida, "On Properties of Magnetite and Serpentine Concrete at Elevated Temperatures for Nuclear Reactor Shielding", Amer. Concr. Inst. Special Publication SP34: Concrete for Nuclear Reactors. Paper SP34-57, Vol. III, 1243-1253 (1972).
  31. B. Wu, J. Yuan, and G.Y. Wang, "Experimental Study on the Mechanical Properties of HSC After High Temperature", Chinese J. Civil Engineering, 33(2), 8-15 (2000).
  32. B.T. Kelly, J.E. Brocklehurst, D. Mottershead, S. McNearney, and I. Davidson, "Effects of reactor radiation on concrete", 2nd Conference on Prestressed Concrete Reactor Pressure Vessels and their Insulation. Commission of the European Communities, Brussels (1968).
  33. L.F. Elleuch, F. Dubois, and J. Rappeneau, "Effects of neutron radiation on special concretes and their components", American Concrete Institute Special Publication SP-34:Concrete for Nuclear Reactors. Paper SP 34-51, 1071-108 (1972).
  34. J. Seeberger and H.K. Hilsdorf, "Effect of nuclear radiation on mechanical properties of concrete", Transactions 5th International Conference on Structural Mechanics in Reactor Technology (SMIRT-5), Paper H2/3, North-Holland (1979).
  35. V.B Dubrovskii, Sh.Sh. Ibragimov, M.Ya. Kulakovskii, A.Ya. Ladygin, and B.K. Pergamenshchik, "Radiation damage in ordin da concrete", Atomnina Energina, 23(4), 310-16, English translation in Soviet Atomic Energy, 23(4), 1053-8 (1967).
  36. H.K. Hilsdorf, J. Kropp, and H.J. Koch, "The effects of nuclear radiation on the mechanical properties of concrete", American Concrete Institute Special Publication SP-55, Paper SP55-10, 223-51 (1978).
  37. S.C. Alexander, "Effects of Irradiation on Concrete: Final Results", Atomic Energy Research Establishment, Harwell, United Kingdom Atomic Energy Authority (1963).
  38. G. Edgemon and R. Anantatmula, "Hanford Waste Tank System Degradation Mechanisms", WHC-SD-WM-ER-414, Rev. 0a, Hanford, June 26 (1995).
  39. D.L. Fillmore, "Literature Review of the Effects of Radiation and Temperature on the Aging of Concrete", Idaho National Engineering and Environmental Laboratory, INEEL/EXT-04-02319, 1-10 (2004).
  40. J.A. Houben, "De bestraling van Mortelproefstukken (The irradiation of mortar test specimens", 2nd Conference on Prestressed Concrete Reactor Vessels and their Thermal Insulation, Commission of the European Communities, Brussels (November) (1969).
  41. C.F. Van der Schaaf, "Effect of irradiation and heating on the strength of mortar and concrete)", 2nd Conference on Prestressed Concrete Reactor Vessels and their Thermal Insulation, Commission of the European Communities, Brussels (November) (1969).
  42. S. Granata and A. Montagnini, "Studies of behaviour of concrete under irradiation", Amer. Concr. Inst. Special Publication SP-34: Concrete for nuclear reactors, Paper SP34-53, Vol. II, 1163-72 (1972).
  43. B.S. Gray, "The effect of reactor radiation on cements and concrete", Conference on Prestressed Concrete Reactor Pressure Vessels, Commission of the European Communities, Luxembour, 17-39 (1972).
  44. US. Nuclear Regulatory Commission, 10CFR 72.104-Criteria for radioactive materials in effluents and direct radiation from ISFSI or MRS (1998).
  45. US. Nuclear Regulatory Commission, 10CFR 72.106-Controlled area of an ISFSI or MRS (2017).
  46. Organization of Economic Co-operation and Development, "Radiological Impact of Spent Nuclear Fuel Management Options-A Comparative Study", Nuclear Energy Agency for the OECD (2000).
  47. G. Edgemon and R. Anantatmula, "Hanford Waste Tank System Degradation Mechanisms", WHC-SD-WM-ER-414, Rev. 0a, Hanford, June 26 (1995).
  48. Jager, R. G.(ed.), Engineering Compendium on Radiation Shielding, Vol. II. Springer-Verlag, New York, 117 (1975).
  49. US Nuclear Regulatory Commission, The Effect of Elevated Temperature on Concrete Materials and Structures - A Literature Review, NUREG/CR-6900, ORNL/TM-2005/553, Oak Ridge National Laboratory (2006).
  50. American Society of Mechanical Engineers. "Boiler and Pressure Vessel Code-Section III: Rules for construction of nuclear power plant components", American Society of Mechanical Engineers, New York (2007).
  51. Electric Power Research Institute, Used fuel and high-level radioactive waste extended storage collaboration program: November 2009 workshop proceedings, TR-1020780, Palo Alto, California: EPRI (2010).
  52. ASTM International, "Standard guide for evaluation of materials used in extended service of interim spent nuclear fuel dry storage systems", ASTM C1562-10, West Conshohocken, Pennsylvania: ASTM International (2010).
  53. Southwest Research Institute, Initial Long-term Integrity Assessment of Spent Fuel Dry Storage-Final Report, Center for Nuclear Waste Regulatory Analyses, Geosciences and Engineering Division, SRI, CNWRA 2011-001, Texas, USA (2011).
  54. H.E. Hungerford, "Shielding,' Ch. 8 in Fast Reactor Technology: Plant Design", Yevick, J.G. (ed.), MIT Press, Cambridge, Massachusetts, 432 (1966).
  55. American National Standard Institute, Nuclear Analysis and Design of Concrete Radiation Shielding for Nuclear Power Plants, ANSI/ANS-6.4-2006 (2006).
  56. British Standards Institution, "Specification for Prestressed concrete Pressure Vessels for Nuclear Reactors", BS 4975, London (1990).
  57. L.F. Elleuch, F. Dubois, and J. Rappeneau, "Effects of neutron radiation on special concretes and their components", American Concrete Institute Special Publication SP-34:Concrete for Nuclear Reactors, Paper SP 34-51, 1071-108 (1972).

Cited by

  1. Coefficient of Thermal Expansion of RCA Concrete Made by Equivalent Mortar Volume vol.11, pp.17, 2018, https://doi.org/10.3390/app11178214