Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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A new approach to quantify safety benefits of disaster robots

  • Received : 2016.07.25
  • Accepted : 2017.06.04
  • Published : 2017.10.25
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Abstract

Remote response technology has advanced to the extent that a robot system, if properly designed and deployed, may greatly help respond to beyond-design-basis accidents at nuclear power plants. Particularly in the aftermath of the Fukushima accident, there is increasing interest in developing disaster robots that can be deployed in lieu of a human operator to the field to perform mitigating actions in the harsh environment caused by extreme natural hazards. The nuclear robotics team of the Korea Atomic Energy Research Institute (KAERI) is also endeavoring to construct disaster robots and, first of all, is interested in finding out to what extent safety benefits can be achieved by such a disaster robotic system. This paper discusses a new approach based on the probabilistic risk assessment (PRA) technique, which can be used to quantify safety benefits associated with disaster robots, along with a case study for seismic-induced station blackout condition. The results indicate that to avoid core damage in this special case a robot system with reliability > 0.65 is needed because otherwise core damage is inevitable. Therefore, considerable efforts are needed to improve the reliability of disaster robots, because without assurance of high reliability, remote response techniques will not be practically used.

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References

  1. S.H. Kim, K.M. Jung, S.U. Lee, H.C. Shin, C.H. Kim, Y.C. Seo, Y.G. Bae, Innovative robot technologies for nuclear power plant inspection and maintenance, in: ICONE22, Int. Conf. Nucl. Engr., July 7-11, 2014. Prague.
  2. R.R. Murphy, Disaster Robotics, The MIT Press, Cambridge, MA, 2014.
  3. B. Siciliano, O. Khatib (Eds.), Springer Handbook of Robotics, Springer-Verlag, Berlin, 2008.
  4. B.S. Dhillon, Robot Reliability and Safety, Springer-Verlag, New York, 1991.
  5. DARPA Robotics Challenge (DRC), [Internet]. 2015. Available from: www.darpa.mil/program/darpa-robotics-challenge. [Accessed June 23, 2017]
  6. Y. Choi, K.M. Jeong, I.S. Kim, Strategy to Enhance Applicability of the KAERI's Remote Response Technology, Trans Am Nucl Soc, San Antonio, TX, June 7-11, 2015.
  7. M. Modarres, What Every Engineer Should Know About Reliability and Risk Analysis, Marcel Dekker, New York, 1993.
  8. M. Modarres, I.S. Kim, Deterministic and probabilistic safety analysis, in: D.G. Cacuci (Ed.), Handbook of Nuclear Engineering, Springer Science, New York, 2010, pp. 1742-1812.
  9. Nuclear Energy Institute, B.5.b Phase 2 & 3 Submittal Guideline, NEI-06-12, Rev. 3, Nuclear Energy Institute, Washington, DC, 2009.
  10. Nuclear Energy Institute, Diverse and Flexible Coping Strategies (FLEX) Implementation Guide, NEI-12-06, Nuclear Energy Institute, Washington, DC, 2012.
  11. ASME/ANS RA-Sa-2009, Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications, American Society of Mechanical Engineers, New York, 2009.
  12. U.S. Nuclear Regulatory Commission, State-of-the-Art Reactor Consequence Analyses (SOARCA) Report, NUREG-1935, U.S. Nuclear Regulatory Commission, Washington, DC, 2012.
  13. Institute of Nuclear Power Operations (INPO), Special Report on the Nuclear Accident at the Fukushima Daiichi Nuclear Power Station, INPO 11-1005, INPO, Atlanta (GA), 2011.
  14. Arizona Public Service Company, APS Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-design-basis External Events, Arizona Public Service Company, Phoenix (AZ), February 28, 2013.
  15. J.A. Julius, J. Grobbelaar, K. Kohlhepp, Advancing human reliability analysis methods for external events with a focus on seismic, in: Probabilistic Safety Assessment and Management, PSAM12, June 22-27, 2014. Hawaii.
  16. U.S. Nuclear Regulatory Commission, Reevaluation of Station Blackout Risk at Nuclear Power Plants, Analysis of Loss of Power Events: 1986-2004, NUREG/CR-6890, U.S. Nuclear Regulatory Commission, Washington, DC, 2005.
  17. M.V.D. Borst, H. Schoonakker, An overview of PSA importance measures, Rel. Engr. Sys. Saf. 72 (2001) 241-245. https://doi.org/10.1016/S0951-8320(01)00007-2
  18. J.-E. Holmberg, U. Pulkkinen, T. Rosqvist, K. Simola, Decision Criteria in PSA Applications, VTT Automation, Finland, 2001.
  19. U.S. Nuclear Regulatory Commission, Systems Analysis Programs for Handson Integrated Reliability Evaluations (SAPHIRE) Version 8, NUREG/CR-7039, U.S. Nuclear Regulatory Commission, Washington, DC, 2011.
  20. U.S. Nuclear Regulatory Commission, Systems Analysis Programs for Hands-on Integrated Reliability Evaluations (SAPHIRE) Version 8, NUREG/CR-7039, U.S. Nuclear Regulatory Commission, Washington, DC, 2011.

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