Transactions of the Korean hydrogen and new energy society (한국수소및신에너지학회논문집)

The Korean Hydrogen and New Energy Society (한국수소및신에너지학회)
권호 표지
DOI QR코드

DOI QR Code

Safety Analysis of a Hydrogen Isotopes Process

수소동위원소 공정 안전해석

  • 정흥석 (한국원자력연구원 핵주기공정개발부) ;
  • 강현구 (국가핵융합연구소 이터한국사업단) ;
  • 장민호 (국가핵융합연구소 이터한국사업단) ;
  • 조승연 (국가핵융합연구소 이터한국사업단) ;
  • 김원국 (RMS HAZOP팀) ;
  • 남재연 (RMS HAZOP팀) ;
  • 김덕진 (TUV SUD KOCEN SDS팀) ;
  • 송규민 (KHNP 중앙연구원) ;
  • 백승우 (한국원자력연구원 핵주기공정개발부) ;
  • 구대서 (한국원자력연구원 핵주기공정개발부) ;
  • 정동유 (한국원자력연구원 핵주기공정개발부) ;
  • 이정민 (한국원자력연구원 핵주기공정개발부) ;
  • 김창석 (국가핵융합연구소 이터한국사업단) ;
  • 정기정 (국가핵융합연구소 이터한국사업단) ;
  • 윤세훈 (국가핵융합연구소 이터한국사업단)
  • Received : 2012.05.31
  • Accepted : 2012.06.22
  • Published : 2012.06.30
Download PDF
⟨ Previous Next ⟩

Abstract

A nuclear fusion fuel cycle plant is composed of various subsystems such as a hydrogen isotope storage and delivery system, a tokamak exhaust processing system, and a hydrogen isotope separation system. Korea shares in the construction of the International Thermonuclear Experimental Reactor fuel cycle plant with the EU, Japan and US, and is responsible for the development and supply of the storage and delivery system. We thus present details on the hydrogen isotope process safety. The main safety analysis procedure is to use a hazard and operability study. Nine segments were studied how the plant might deviate from its design purpose. We present a detailed description of the process, examine every part of it to determine how deviations from the design intent can occur and decide whether these deviations can give rise to hazards. We determine possible causes and note protective systems, evaluate the consequences of the deviation, and recommend actions to achieve our safety goal.

Keywords

References

  1. H. Chung, M. Shim, D. Ahn, M. Lee, C. Hong, H. Yoshida, K. Song, D. Kim, K. Jung, and S. Cho, "Korea's Activities for the Development of ITER Tritium Storage and Delivery Systems", Fusion Science and Technology, Vol. 54, 2008, p. 18. https://doi.org/10.13182/FST08-38
  2. M. Shim, H. Chung, S. Cho, and H. Yoshida, "Disproportionation Characteristics of a Zirconium- Cobalt Hydride Bed under ITER Operating Conditions", Fusion Science and Technology, Vol. 53, 2008, p. 830. https://doi.org/10.13182/FST08-26
  3. M. Shim, H. Chung, H. Yoshida, H. Jin, M. Chang, S. Yun, and S. Cho, "Initial Test Results of a Fast Heat Transfer Response ZrCo Hydride Bed", Fusion Science and Technology, Vol. 56, 2009, p. 857.
  4. M. Shim, H. Chung, H. Yoshida, K. Kim, S. Cho, E. Lee, and M. Chang, "Experimental Study on the Delivery Rate and Recovery Rate of ZrCo Hydride for ITER Application", Fusion Science and Technology, Vol. 54, 2008, p. 27. https://doi.org/10.13182/FST08-39
  5. M. Shim, H. Chung, H. Yoshida, H. Jin, J. Lee, K. Song, M. Chang, H. Kang, S. Yun, and S. Cho, "Hydriding/dehydriding Characteristics on Fast Heat Transfer Response ZrCo Bed for ITER", Fusion Engineering and Design, Vol. 84, 2009, p. 1763. https://doi.org/10.1016/j.fusengdes.2008.11.006
  6. M. Shim, H. Chung, K. Kim, H. Yoshida, S. Cho, D. Kim, and M. Ahn, "Heat analysis on the initial reference design of ZrCo hydride beds for ITER", Fusion Engineering and Design, Vol. 83, 2008, p. 1433. https://doi.org/10.1016/j.fusengdes.2008.06.035
  7. D. Chung, D. Jeong, D. Koo, H. Yoshida, K. Song, M. Chang, H. Kang, S. Yun, S. Cho, K. Jung, and H. Chung, "Fusion fuel gas recovery and delivery characteristics on a tray-type ZrCo bed", Fusion Engineering and Design, Vol. 86, 2011, p. 2233. https://doi.org/10.1016/j.fusengdes.2010.11.026
  8. H. Chung, D. Chung, D. Koo, J. Lee, M. Shim, S. Cho, K. Jung, S. Yun, "Storage and Delivery of Hydrogen Isotopes", Trans. of the Korean Hydrogen and New Energy Society, Vol. 22, No. 3, 2011, pp. 372-379.
  9. D. Koo, H. Chung, D. Chung, J. Lee, S. Yun, S. Cho, K. Jung, "Hydrogen Isotopes Accountancy and Storage Technology", Trans. of the Korean Hydrogen and New Energy Society, Vol. 23, No. 1, 2012, pp. 49-55. https://doi.org/10.7316/khnes.2012.23.1.049
  10. S. Yun, M. Chang, H. Kang, C. Kim, S. Cho, K. Jung, H. Chung, K. Song, "Tritium Fuel Cycle Technology of ITER Project", Trans. of the Korean Hydrogen and New Energy Society, Vol. 23, No. 1, 2012, pp. 56-64. https://doi.org/10.7316/khnes.2012.23.1.056
  11. K. Song, S. Sohn, Y. Chung, S. Cho, D. Kim, M. Ahn, M. Shim, H. Chung, D. Kim, and H. Yoshida, "The development of standard operating procedures for the SDS of the ITER tritium plant", Fusion Engineering and Design, Vol. 83, 2008, p. 1380. https://doi.org/10.1016/j.fusengdes.2008.08.007
  12. M. Glugla, A. Busigin, L. Doerr, R. Haange, T. Hayashi, O. Kveton, R. Laesser, D.K. Murdoch, M. Nishi, R.-D. Penzhorn, and H. Yoshida, "The tritium fuel cycle of ITER-FEAT", Fusion Engineering and Design, Vol. 58-59, 2001, p. 349. https://doi.org/10.1016/S0920-3796(01)00356-8
  13. M. Glugla, C. Caldwell-Nichols, I.R. Cristescu, L. Do¨rr, G. Hellriegel, R. Laesser, D. Murdoch, and P. Schaefer, "Protection of the primary circuits and effect on the design of the inner deuterium /tritium fuel cycle of ITER", Fusion Engineering and Design, Vol. 75-79, 2005, p. 637. https://doi.org/10.1016/j.fusengdes.2005.06.047
  14. S. Lee, J. Uhm, K. Oh, J. Choi, J. Paek, D. Ha, "Gas Safety Engineering", Donghwapub, Gyeonggido, 2009, pp. 367-371.
  15. S. Banerjee, "Industrial Hazards and Plant Safety", Taylor & Francis, New York, 2003, pp. 65-85.
  16. J.J. Kats and E Rabinowitch, "The Chemistry of Uranium", Dover Publications,, New York, 1951, pp. 164-203.
  17. T. B. Massalski, "Binary alloy phase diagrams", 2nd ed., Alloy Phase Diagram International Commission, 1990, pp. 1787-1789.
  18. E.H.P. Cordfunke, "The Chemistry of Uranium", Elsevier, Amsterdam, 1969, p. 62.
  19. H. Chung,, M. Shim, D. Ahn, M. Lee, C. Hong, H. Yoshida, K. Song, D. Kim, K. Jung, and S. Cho, "Korea's activities for the development of a detritiation system", Fusion Science and Technology, Vol. 56, 2009, p. 141. https://doi.org/10.13182/FST09-A8891
  20. K. Okayama., D. van Houtte, F. Sagot, and S. Maruyama, "RAMI analysis for ITER fuel cycle system", Fusion Engineering and Design, Vol. 86, 2011, p. 598. https://doi.org/10.1016/j.fusengdes.2011.01.121
  21. Ihn Namgung, H.G. Kang, M.H. Chang, C.H. Kim, S.H. Yun, and K.J. Jung, "Reliability Analysis Modeling of ITER Tritium Storage and Delivery System at Conceptual Design Stage", Transactions of the Korean Nuclear Society Spring Meeting, 2012, p. 862.
  22. Woo-seok Choi, Jae-han Lee, Seungyon Cho, and Sei-hun Yun, "Load Specification and Seismic Analysis for ITER Tritium SDS", Transactions of the Korean Nuclear Society Spring Meeting, 2012, p. 860.

Cited by

  1. Rapid Cooling Performance Evaluation of a ZrCo bed for a Hydrogen Isotope Storage vol.24, pp.2, 2013, https://doi.org/10.7316/KHNES.2013.24.2.128
  2. Hydrogen Absorption/Desorption and Heat Transfer Modeling in a Concentric Horizontal ZrCo Bed vol.24, pp.4, 2013, https://doi.org/10.7316/KHNES.2013.24.4.295
  3. Fusion Licensing and Safety Studies in Korea vol.42, pp.3, 2014, https://doi.org/10.1109/TPS.2013.2288789
  4. Characteristics of a Hydrogen Isotope Storage and Accountancy System vol.26, pp.6, 2015, https://doi.org/10.7316/KHNES.2015.26.6.541
  5. Dehydriding Performance in a Depleted Uranium Bed vol.27, pp.1, 2016, https://doi.org/10.7316/KHNES.2016.27.1.022