Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Fracture simulation of SFR metallic fuel pin using finite element damage analysis method

  • Jung, Hyun-Woo (Korea University, Department of Mechanical Engineering) ;
  • Song, Hyun-Kyu (Korea University, Department of Mechanical Engineering) ;
  • Kim, Yun-Jae (Korea University, Department of Mechanical Engineering) ;
  • Jerng, Dong-Wook (Chung-ang University, Department of Energy Systems Engineering)
  • Received : 2020.04.06
  • Accepted : 2020.08.06
  • Published : 2021.03.25
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Abstract

This paper suggests a fracture simulation method for SFR metallic fuel pin under accident condition. Two major failure mechanisms - creep damage and eutectic penetration - are implemented in the suggested method. To simulate damaged element, stress-reduction concept to reduce stiffness of the damaged element is applied. Using the proposed method, the failure size of cladding can be predicted in addition to the failure time and failure site. To verify the suggested method, Whole-pin furnace (WPF) test and TREAT-M test conducted at Argonne National Laboratory (ANL) are simulated. In all cases, predicted results and experimental results are overall in good agreement. Based on the simulation result, the effect of eutectic-penetration depth representing failure behavior on failure size is studied.

Keywords

Acknowledgement

This research was supported by the National Research Foundation of Korea (NRF) funded by the Ministry of Science and ICT. (NRF2013M2B2B1075733).

References

  1. J.E. Cahalan, J.M. Kramer, J.F. Marchaterre, C.J. Mueller, D.R. Pedersen, R.H. Sevy, D.C. Wade, T.Y.C. Wei, Integral Fast Reactor Safety Features, No. CONF-880506-12, Argonne National Laboratory, Argonne, USA, 1988.
  2. K.J. Miles Jr., A.M. Tentner, Metal Fuel Safety Performance, No. CONF-880506- 18, Argonne National Lab, Argonne, USA, 1988.
  3. A.M. Tentner, E. Parma, T. Wei, R. Wigeland, Severe Accident Approach - Final Report. Evaluation of Design Measures for Severe Accident Prevention and Consequence Mitigation, No. ANL-GENIV-128, Argonne National Laboratory, Argonne, USA, 2010, https://doi.org/10.2172/973483.
  4. T.H. Bauer, A.E. Wright, W.R. Robinson, J.W. Holland, E.A. Rhodes, Behavior of modern metallic fuel in treat transient overpower tests, Nucl. Tech. 92 (3) (1990) 325-352, https://doi.org/10.13182/NT92-325.
  5. H. Heo, S.D. Park, D.W. Jerng, I.C. Bang, Visual study of ex-pin phenomena for SFR with metal fuel under initial phase of severe accidents by using simulants, J. Nucl. Sci. Technol. 53 (9) (2016) 1409-1416, https://doi.org/10.1080/00223131.2015.1120246.
  6. M.H. Lee, H. Hyo, I.C. Bang, D.W. Jerng, Effect of rupture size in Ex-pin phenomena of severe accident in SFR, in: Proceedings of 2017 International Congress on Advances in Nuclear Power Plants, Fukui and Kyoto, Japan, April 24-28, 2017.
  7. M.H. Lee, H. Hyo, D.W. Jerng, I.C. Bang, Phenomenological study on the Ex-pin phenomenain theinitial phase of HCDA onmetal-fueled SFR using simulant, Ann. Nucl. Energy 130 (2019) 34-46, https://doi.org/10.1016/j.anucene.2019.02.024.
  8. T. Sofu, J.M. Kramer, The SAS4A/SASSYS-1 Safety Analysis Code System, Chapter 11: FPIN2 Pre-failure Metal Fuel Pin Behavior Model, No. ANL/NE-16/19, Argonne National Laboratory, Argonne, USA, 2017.
  9. A. Biancheria, T.S. Roth, B.E. Sundquist, Steady-state and transient fuel performance modelling: LIFE-4 update, in: Proceedings of International Conference on Reliable Fuels for Liquid Metal Reactors 5.1-5.14, Tucson, USA, September 7-11, 1986.
  10. A. Karahan, Modeling of Thermos-Mechanical and Irradiation Behavior of Metallic and Oxide Fuels for Sodium Fast Reactors, Doctoral thesis, Massachusetts Institute of Technology, Cambridge, USA, 2009.
  11. Dassault Systems, Abaqus Version 2016 Manual, Velizy-Villacoublay, France, 2015.
  12. Y.Y. Liu, H.C. Tsai, D.A. Donahue, D.O. Pushis, F.E. Savoie, J.W. Holland, A.E. Wright, C. August, J.L. Bailey, D.R. Patterson, Whole-pin furnace system: an experimental facility for studying irradiated fuel pin behavior under potential reactor accident conditions, in: Proceedings of ANS Topical Meeting on Fast Reactor Safety 491, Snowbird, USA, August 12-16, 1990.
  13. Y.Y. Liu, H.C. Tsai, M.C. Billone, J.W. Holland, J.M. Kramer, Behavior of EBR-II Mk-V-type fuel elements in simulated loss-of-flow tests, J. Nucl. Mater. 204 (1993) 194-202, https://doi.org/10.1016/0022-3115(93)90217-M.
  14. J.M. Kramer, Y.Y. Liu, M.C. Billone, H.C. Tsai, Modeling the behavior of metallic fast reactor fuels during extended transients, J. Nucl. Mater. 204 (1993) 203-211, https://doi.org/10.1016/0022-3115(93)90218-N.
  15. W.R. Robinson, R.K. Lo, A.E. Wright, T.H. Bauer, G.S. Stanford, J.A. Morman, Integral fast reactor safety tests M2 and M3 in TREAT, in: Proceedings of ANS Winter Meeting, 50, November 10, 1985, pp. 352-353. San Francisco, USA.
  16. W.R. Robinson, T.H. Bauer, A.E. Wright, E.A. Rhodes, G.S. Stanford, A.E. Klickman, First TREAT transient overpower tests on U-Pu-Zr fuel:M5 and M6, Trans. Am. Nucl. Soc. 55 (1987) 418.
  17. N.E. Toredas, M.S. Kazimi, Nuclear Systems: Thermal Hydraulic Fundamentals, CRC press, Boca Raton, USA, 2012.
  18. L. Leibowitz, R.A. Blomquist, Thermal conductivity and thermal expansion of stainless steels D9 and HT9, Int. J. Thermophys. 9 (5) (1988) 873-883, https://doi.org/10.1007/BF00503252.
  19. J.K. Fink, L. Leibowitz, Thermodynamic and Transport Properties of Sodium Liquid and Vapor, No. ANL/RE-95/2, Argonne National Laboratory, Argonne, USA, 1995.
  20. N. Yamanouchi, M. Tamura, H. Hayakawa, A. Hishinuma, T. Kondo, Accumulation of engineering data for practical use of reduced activation ferritic steel: 8%Cr-56-2%W-0.2%V-0.04%Ta-Fe, J. Nucl. Mater. 191 (1992) 822-826, https://doi.org/10.1016/0022-3115(92)90587-B.
  21. A. Banerjee, S. Raju, R. Divakar, E. Mohands, High temperature heat capacity of alloy D9 using drop calorimetry based enthalpy increment measurements, Int. J. Thermophys. 28 (1) (2007) 97-108, https://doi.org/10.1007/s10765-006-0136-0.
  22. S. Sharafat, R. Amodeo, N.M. Ghoniem, Materials Data Base and Design Equations for the UCLA Solid Breeder Blanket, No. UCLA-ENG-8611/PPG-937, California University, Los Angenles, USA, 1986.
  23. K.J. Miles, The SAS4A/SASSYS-1 Safety Analysis Code System. Chapter 9: DEFORM-5 Metallic Fuel Cladding Transient Behavior Model, No. ANL/NE-16/19, Argonne National Laboratory, Argonne, USA, 2017.
  24. R.J. Dimelfi, J.M. Kramer, Modeling the effects of fast-neutron irradiation of the subsequent mechanical behavior of type 316 stainless steel, J. Nucl. Mater. 89 (1980) 338-346, https://doi.org/10.1016/0022-3115(80)90065-3.
  25. J.M. Kramer, R.J. Dimelfi, Modeling deformation and failure of fast reactor cladding during simulated accident transients, Nucl. Eng. Des. 63 (1) (1981) 47-54, https://doi.org/10.1016/0029-5493(81)90016-9.
  26. Bj Makenas, Swelling of 316 Stainless Steel and D9 Cladding in FFTF, No. ASTM-Stp33814s, American Society for Testing and Materials, Philadelphia, USA, 1987, https://doi.org/10.1520/STP33814S.
  27. T.H. Bauer, G.R. Fenske, J.M. Kramer, Cladding failure margins for metallic fuel in the integral fast reactor, in: Proceedings of International Conference on Structural Mechanics in Reactor Technology, August 17, 1987. Lausanne, Switzerland.
  28. A.B. Cohen, H. Tsai, L.A. Neimark, Fuel/cladding compatibility in U-19Pu-10Zr/HT9-clad fuel at elevated temperatures, J. Nucl. Mater. 204 (1993) 244-251, https://doi.org/10.1016/0022-3115(93)90223-L.
  29. H. Tsai, Fuel/cladding Compatibility in Irradiated Metallic Fuel Pins at Elevated Temperatures. in: Proceedings of ANS Topical Meeting on Fast Reactor Safety 257, Snowbird, USA, August 12-16, 1990.
  30. H.W. Ryu, K.D. Bae, Y.J. Kim, J.J. Han, J.S. Kim, P.J. Budden, Ductile tearing simulation of Battelle pipe test using simplified stress-modified fracture strain concept, Fatig. Fract. Eng. Mater. Struct. 39 (2016) 1391-1406, https://doi.org/10.1111/ffe.12456.
  31. N.H. Kim, C.S. Oh, Y.J. Kim, C.M. Davies, K. Nikbin, D.W. Dean, Creep failure simulations of 316H at 550℃: Part II - effects of specimen geometry and loading mode, Eng. Fract. Mech. 105 (2013) 169-181, https://doi.org/10.1016/j.engfracmech.2013.04.001.
  32. T. Kobayashi, M. Kinoshita, S. Hattori, T. Ogawa, Y. Tsuboi, M. Ishida, S. Ogawa, H. Saito, Development of the SESAME metallic fuel performance code, Nucl. Tech. 89 (2) (1990) 183-193, https://doi.org/10.13182/NT90-A34345.
  33. T. Ogata, T. Yokoo, Development and validation of ALFUS: an irradiation behavior analysis code for metallic fast reactor fuels, Nucl. Technol. 128 (1) (1999) 113-123, https://doi.org/10.13182/NT99-A3018.