Nuclear Engineering and Technology

  • 제49권7호
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  • Pages.1547-1554
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  • 2017
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  • 1738-5733(pISSN)
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  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
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Corium melt researches at VESTA test facility

  • 투고 : 2016.09.12
  • 심사 : 2017.06.19
  • 발행 : 2017.10.25
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초록

VESTA (Verification of Ex-vessel corium STAbilization) and VESTA-S (-small) test facilities were constructed at the Korea Atomic Energy Research Institute in 2010 to perform various corium melt experiments. Since then, several tests have been performed for the verification of an ex-vessel core catcher design for the EU-APR1400. Ablation tests of an impinging $ZrO_2$ melt jet on a sacrificial material were performed to investigate the ablation characteristics. $ZrO_2$ melt in an amount of 65-70 kg was discharged onto a sacrificial material through a well-designed nozzle, after which the ablation depths were measured. Interaction tests between the metallic melt and sacrificial material were performed to investigate the interaction kinetics of the sacrificial material. Two types of melt were used: one is a metallic corium melt with Fe 46%, U 31%, Zr 16%, and Cr 7% (maximum possible content of U and Zr for C-40), and the other is a stainless steel (SUS304) melt. Metallic melt in an amount of 1.5-2.0 kg was delivered onto the sacrificial material, and the ablation depths were measured. Penetration tube failure tests were performed for an APR1400 equipped with 61 in-core instrumentation penetration nozzles and extended tubes at the reactor lower vessel. $ZrO_2$ melt was generated in a melting crucible and delivered down into an interaction crucible where the test specimen is installed. To evaluate the tube ejection mechanism, temperature distributions of the reactor bottom head and in-core instrumentation penetration were measured by a series of thermocouples embedded along the specimen. In addition, lower vessel failure tests for the Fukushima Daiichi nuclear power plant are being performed. As a first step, the configuration of the molten core in the plant was investigated by a melting and solidification experiment. Approximately 5 kg of a mixture, whose composition in terms of weight is $UO_2$ 60%, Zr 10%, $ZrO_2$ 15%, SUS304 14%, and $B_4C$ 1%, was melted in a cold crucible using an induction heating technique.

키워드

참고문헌

  1. H.Y. Kim, Introduction of VESTA (Verification of Ex-vessel corium STAbilization) facility and first series experiment, in: MCCI-2 Project Seminar 2010, Cadarache France, 2010.
  2. H.Y. Kim, J.H. Song, J.H. Kim, R.J. Park, K.S. Ha, Pre-operational Test Report for the Test Facility of Ex-vessel Corium Arresting Device, S07NJ06-R-TR-029, KAERI, 2010.
  3. H.Y. Kim, J.H. Kim, B.T. Min, S.W. Hong, R.J. Park, J.H. Song, Introduction of VESTA facility and melting test results, Proc. Korean Nucl. Soc. Spring Meet., Taebaek, Korea, May 26-27, 2011.
  4. S.M. An, K.S. Ha, B.T. Min, S.H. Hong, H.Y. Kim, An experimental investigation of corium jet impingement on structural material, Proc. Korean Nucl. Soc. Autumn Meet., Gyeongju, Korea, Oct. 24-25, 2013.
  5. S.M. An, K.S. Ha, B.T. Min, H.Y. Kim, J.H. Song, Ablation characteristics of special concrete due to an impinging zirconium-dioxide melt jet, Nucl. Eng. Des. 284 (2015) 10-18. https://doi.org/10.1016/j.nucengdes.2014.10.024
  6. S.M. An, K.S. Ha, B.T. Min, H.Y. Kim, J.H. Song, Experimental investigation of the interaction kinetics between metallic melt and special concrete, Nucl. Technol. 189 (2015) 133-142. https://doi.org/10.13182/NT14-24
  7. S.M. An, J. Jung, K.S. Ha, H.W. Kim, Experimental investigation on APR1400 in-core instrumentation penetration failure during a severe accident, Proc. Int. Congr. Adv. Nucl. Power Plants (ICAPP-2015), Nice, France, May 3-6, 2015.
  8. S.M. An, J. Jung, H. Y. Kim, Experimental investigation on the APR1400 in-core instrumentation penetration failure, Proc. Korean Nucl. Soc. Autumn Meet., Gyeongju, Korea, Oct. 29-30, 2015.
  9. S.M. An, H.Y. Kim, Evaluation of tube ejection failure for APR1400 ICI penetration at various experimental conditions, Proc. Korean Nucl. Soc. Spring Meet., Jeju, Korea, May 12-13, 2016.
  10. S.M. An, J. Jung, H.Y. Kim, APR1400 in-core instrumentation penetration failure by zirconia melt, Proc. American Nucl. Soc. Annu. Meet. 2016, New Orleans, USA, Jun. 12-16, 2016.
  11. J.L. Rempe, S.A. Chavez, G.L. Thinnes, G.M. Allison, G.E. Korth, R.J. Witt, J.J. Sienicki, S.K. Wang, L.A. Stickler, C.H. Heath, S.D. Snow, Light Water Reactor Lower Head Failure Analysis, NUREG/CR-5642, 1993.
  12. S.M. An, B.T. Min, H.Y. Kim, A State-of-the-art Review on Reactor Pressure Vessel Lower Head Penetration Failure Estimation, Technical Report, KAERI/AR-96, 2013.
  13. S.M. An, J.H. Song, J.Y. Kim, H.Y. Kim, M. Naitoh, Experimental investigation on molten pool representing corium composition at Fukushima Daiichi nuclear power plant, J. Nucl. Mater. 478 (2016) 164-171. https://doi.org/10.1016/j.jnucmat.2016.06.011
  14. V.S. Granovsky, А.A. Sulatsky, V.B. Khabensky, М.B. Sulatskaya, V.V. Gusarov, V.I. Almyashev, А.A. Komlev, S. Bechta, Y.S. Kim, R.J. Park, H.Y. Kim, J.H. Song, Modeling of melt retention in EU-APR1400 ex-vessel core catcher, Proc. Int. Congr. Adv. Nucl. Power Plants (ICAPP-2012), Chicago, USA, Jun. 24-28, 2012.
  15. S.M. An, K.S. Ha, B.T. Min, S.H. Hong, H.Y. Kim, Experimental methodology for structural material ablation by corium jet impingement, Proc. Korean Nucl. Soc. Spring Meet., Gwangju, Korea, May 30-31, 2013.
  16. K.S. Ha, S.M. An, B.T. Min, H.Y. Kim, Cold crucible technique for interaction test of molten corium with structure, Proc. Korean Nucl. Soc. Autumn Meet., Gyeongju, Korea, Oct. 25-26, 2012.
  17. S.M. An, K.S. Ha, S.H. Hong, H.Y. Kim, Y. Cha, Interaction experiments of molten corium with structures in a severe accident, Proc. Int. Congr. Adv. Nucl. Power Plants (ICAPP-2014), Charlotte, USA, Apr. 6-9, 2014.
  18. S.M. An, K.S. Ha, H.Y. Kim, An experimental investigation on APR1400 penetration weld failure by metallic melt, Proc. Korean Nucl. Soc. Autumn Meeting, Pyeongchang, Korea, Oct. 30-31, 2014.

피인용 문헌

  1. Experimental investigations on melt coolability with simulated decay heat-The influence of delay time in flooding vol.51, pp.1, 2017, https://doi.org/10.1002/htj.22306