Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
권호 표지
DOI QR코드

DOI QR Code

DEVELOPMENT OF AN OPERATION STRATEGY FOR A HYBRID SAFETY INJECTION TANK WITH AN ACTIVE SYSTEM

  • Received : 2014.08.18
  • Accepted : 2015.01.24
  • Published : 2015.06.25
⟨ Previous Next ⟩

Abstract

A hybrid safety injection tank (H-SIT) can enhance the capability of an advanced power reactor plus (APR+) during a station black out (SBO) that is accompanied by a severe accident. It may a useful alternative to an electric motor. The operations strategy of the H-SIT has to be investigated to achieve maximum utilization of its function. In this study, the master logic diagram (i.e., an analysis for identifying the differences between an H-SIT and a safety injection pump) and an accident case classification were used to determine the parameters of the H-SIT operation. The conditions that require the use of an H-SIT were determined using a decision-making process. The proper timing for using an H-SIT was also analyzed by using the Multi-dimensional Analysis of Reactor Safety (MARS) 1.3 code (Korea Atomic Energy Research Institute, Daejeon, South Korea). The operation strategy analysis indicates that a H-SIT can mitigate five types of failure: (1) failure of the safety injection pump, (2) failure of the passive auxiliary feedwater system, (3) failure of the depressurization system, (4) failure of the shutdown cooling pump (SCP), and (5) failure of the recirculation system. The results of the MARS code demonstrate that the time allowed for recovery can be extended when using an H-SIT, compared with the same situation in which an H-SIT is not used. Based on the results, the use of an H-SIT is recommended, especially after the pilot-operated safety relief valve (POSRV) is opened.

Keywords

Acknowledgement

Supported by : Korea Institute of Energy Technology Evaluation and Planning (KETEP)

References

  1. Government of Japan, Additional Report of the Japanese Government to the IAEA, Nuclear Emergency Response Headquarters, Government of Japan, Tokyo, Japan, 2011.
  2. J.E. Yang, Fukushima Dai-ichi accidents: lessons learned and future actions from the risk perspective, Nucl. Eng. Technol. 46 (2014) 27-38. https://doi.org/10.5516/NET.03.2014.702
  3. J.H. Song, T.W. Kim, Severe accident issues raised by the Fukushima accident and improvements suggested, Nucl. Eng. Technol. 46 (2014) 207-216. https://doi.org/10.5516/NET.03.2013.079
  4. B.U. Bae, S. Kim, Y.S. Park, K.H. Kang, B.J. Yun, Experimental investigation into the effect of the passive condensation cooling tank water level in the thermal performance of the passive auxiliary feedwater system, Nucl. Technol. 181 (2013) 479-492. https://doi.org/10.13182/NT181-479
  5. A.K. Nayak, R.K. Sinha, Role of passive systems in advanced reactors, Prog. Nucl. Eng. 49 (2007) 486-498. https://doi.org/10.1016/j.pnucene.2007.07.007
  6. V. Jain, A.K. Nayak, M. Dhiman, P. Kulkarni, P.K. Vijayan, K.K. Vaze, Role of passive safety feature in prevention and mitigation of severe plant conditions in Indian advanced heavy water reactor, Nucl. Eng. Technol. 45 (2013) 625. https://doi.org/10.5516/NET.03.2013.013
  7. T.S. Kwon, C.K. Park, Hybrid SIT for Passive Safety System, Transaction of the Korean Nuclear Society Spring Meeting, May 30-31, 2013, Korean Nuclear Society, Daejeon, Korea, 2013.
  8. J.A. Papazoglou, O.N. Aneziris, Master Logic Diagram: method for hazard and initiating event identification in process plants, J. Hazard. Mater. 97 (2003) 11-30. https://doi.org/10.1016/S0304-3894(02)00244-3
  9. Korea Hydro-Nuclear Power (KHNP), Emergency Operating Procedure of APR1400 & APR+, KHNP, Seoul, South Korea, 2011.
  10. W.R. Corcoran, D.J. Finnicum, F.R. Hubbard III, C.R. Musick, P.F. Walzer, The Operator's Role and Safety Functions, Atomic Industrial Forum Workshop on Licensing and Technical Issues-Post TMI, Mar. 9-12, 1980, Atomic Industrial Forum, Washington, DC, 1980.
  11. Korea Atomic Energy Research Institute (KAERI), Procedure for Conducting Probabilistic Safety Assessment, KAERI TR-2548, KAERI, Taejon, Korea, 2003.
  12. W.R. Corcoran, N.J. Porter, J.F. Church, M.T. Cross, W.M. Guinn, The critical safety functions and plant operation, Nucl. Technol. 55 (1981) 690-712. https://doi.org/10.13182/NT81-A32814
  13. R.J. Park, S.B. Kim, S.W. Hong, H.D. Kim, Detailed evaluation of coolant injection into the reactor vessel with RCS depressurization for high pressure sequences, Nucl. Eng. Des. 239 (2009) 2484-2490. https://doi.org/10.1016/j.nucengdes.2009.06.019
  14. H. Buchner, H. Fabian, Comparative evaluation of active vs passive system designs, Reliab. Eng. Syst. Safe. 45 (1994) 195-200. https://doi.org/10.1016/0951-8320(94)90085-X
  15. B.U. Bae, B.J. Yun, S. Kim, K.H. Kang, Design of condensation heat exchanger for the PAFS (Passive Auxiliary Feedwater System) of APR+ (Advanced Power Reactor Plus), Ann. Nucl. Energy 46 (2012) 134-143. https://doi.org/10.1016/j.anucene.2012.03.029
  16. Westinghouse Electric Company, The AP1000 Adverse System Interactions Evaluation Report, Nuclear Regulatory Commission, Washington, DC, 2011.
  17. Nuclear Regulatory Commission, Acceptance Criteria for Emergency Core Cooling Systems for Light-water Nuclear Power Reactors, 10 CFR 50.46, Nuclear Regulatory Commission, Washington, DC, 2014.
  18. R.J. Borkowski, W.K. Kahl, T.L. Hebble, J.R. Fragola, J.W. Johnson, The In-plant Reliability Database for Nuclear Plant Components-the Valve Component, NUREG CR-3154, U.S. Nuclear Regulatory Commission, Washington, DC, 1984.

Cited by

  1. 피동충수용 혼합형 안전주입탱크의 압력평형에 관한 이론적 해석 및 시험적 연구 vol.25, pp.1, 2016, https://doi.org/10.5855/energy.2015.25.1.185
  2. 발전소 정전사고 시 Hybrid SIT의 냉각성능 평가를 위한 안전해석에 관한 연구 vol.26, pp.3, 2015, https://doi.org/10.5855/energy.2017.26.3.064