Nuclear Engineering and Technology

  • 제52권4호
  • /
  • Pages.742-754
  • /
  • 2020
  • /
  • 1738-5733(pISSN)
  • /
  • 2234-358X(eISSN)
한국원자력학회 (Korean Nuclear Society)
권호 표지
DOI QR코드

DOI QR Code

Investigation of a best oxidation model and thermal margin analysis at high temperature under design extension conditions using SPACE

  • Lee, Dongkyu (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • No, Hee Cheon (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology) ;
  • Kim, Bokyung (Department of Nuclear and Quantum Engineering, Korea Advanced Institute of Science and Technology)
  • 투고 : 2019.01.17
  • 심사 : 2019.09.20
  • 발행 : 2020.04.25
PDF 다운로드
⟨ 이전 논문 다음 논문 ⟩

초록

Zircaloy cladding oxidation is an important phenomenon for both design basis accident and severe accidents, because it results in cladding embrittlement and rapid fuel temperature escalation. For this reason during the last decade, many experts have been conducting experiments to identify the oxidation phenomena that occur under design basis accidents and to develop mathematical analysis models. However, since the study of design extension conditions (DEC) is relatively insufficient, it is essential to develop and validate a physical and mathematical model simulating the oxidation of the cladding material at high temperatures. In this study, the QUENCH-05 and -06 experiments were utilized to develop the best-fitted oxidation model and to validate the SPACE code modified with it under the design extension condition. It is found out that the cladding temperature and oxidation thickness predicted by the Cathcart-Pawel oxidation model at low temperature (T < 1853 K) and Urbanic-Heidrick at high temperature (T > 1853 K) were in excellent agreement with the data of the QUENCH experiments. For 'LOCA without SI' (Safety Injection) accidents, which should be considered in design extension conditions, it has been performed the evaluation of the operator action time to prevent core melting for the APR1400 plant using the modified SPACE. For the 'LBLOCA without SI' and 'SBLOCA without SI' accidents, it has been performed that sensitivity analysis for the operator action time in terms of the number of SIT (Safety Injection Tank), the recovery number of the SIP (Safety Injection Pump), and the break sizes for the SBLOCA. Also, with the extended acceptance criteria, it has been evaluated the available operator action time margin and the power margin. It is confirmed that the power can be enabled to uprate about 12% through best-estimate calculations.

키워드

참고문헌

  1. Keyou Mao, Jun Wang, Development of cladding oxidation analysis code [COAC] and application for early stage severe accident simulation of AP1000, Prog. Nucl. Energy 85 (2015) 352-365. https://www.sciencedirect.com/science/article/pii/S0149197015300408. https://doi.org/10.1016/j.pnucene.2015.07.010
  2. IRSN, A state-of-the-art review of past programmes devoted to fuel behavior under Loss-of-Coolant conditions. Part 3", DPAM/SEMCA 2008-093. https://www.irsn.fr/EN/Research/publications-documentation/Publications/DPAM/ SEMCA/Pages/A-state-of-the-art-review-of-past-programs-devoted-to-fuelbehaviour-under-LOCA-conditions-part2-Impact-of-4339.aspx, 2008.
  3. J.V. Cathcart, R.E. Pawel, Zirconium metal-water oxidation kinetics IV, React. Rate Stud. ORNL/NUREG 17 (1977). https://www.nrc.gov/docs/ML0522/ML052230079.pdf.
  4. S. Leistikow, G. Schanz, Oxidation kinetics and related phenomena of Zircaloy-4 fuel cladding exposed to high temperature steam and hydrogen-steam mixtures under PWR accident conditions, Nucl. Eng. Des. 103 (1987) 65-84. https://doi.org/10.1016/0029-5493(87)90286-X.
  5. V.F. Urbanic, T.R. Heidrick, High-temperature oxidation of zircaloy-2 and zircaloy-4 in steam", J. Nucl. Mater. 74 (1978). https://doi.org/10.1016/0022-3115(78)90006-5.
  6. J.T. Prater, E.L. Courtright, Zircaloy-4 Oxidation at 1300 to $2400^{\circ}C$, NUREG/CR-4889, April 1987.
  7. J. Stuckert, M. Steinbruck, M. Grosse, "Experimental program QUENCH at KIT on core degradation during reflooding under LOCA conditions in the early phase of a severe accident", IAEA-TECDOC-CD-1775. https://inis.iaea.org/search/search.aspx?orig_q1/4RN:47035584, 2013, 281-297.
  8. M. Steinbrück, M. Grosse, L. Sepold, J. Stuckert. "Synopsis and outcome of the QUENCH experimental program", Nucl. Eng. Des. 240 (2010) 1714-1727. https://www.sciencedirect.com/science/article/pii/S0029549310001998. https://doi.org/10.1016/j.nucengdes.2010.03.021
  9. L. Sepold, W. Hering, C. Homann, A. Miassoedov, G. Schanz, U. Stegmaier, M. Steinbruck, H. Steiner, J. Stuckert, Experimental and Computational Results of the QUENCH-06 Test (OECD ISP-45), Scientific Report FZKA-6664, February 2004. Karlsruhe, https://publikationen.bibliothek.kit.edu/270057214/3814496.
  10. L. Baker, L.C. Just, Studies of Metal-Water Reactions at High Temperatures; III. Experimental and Theoretical Studies of the Zirconium-Water Reaction, Report ANL-6548, Argonne National Laboratory, May 1962, https://www.nrc.gov/docs/ML0505/ML050550198.pdf.
  11. G. Schanz, B. Adroguer, A. Volchek, Advanced treatment of Zircaloy cladding high-temperature oxidation in severe accident code calculations: Part I. Experimental database and basic modeling, Nucl. Eng. Des. 232 (2004) 75-84, page, https://doi.org/10.1016/j.nucengdes.2004.02. 013.
  12. G. Schanz, Recommendations and Supporting Information on the Choice of Zirconium Oxidation Models in Severe Accident Codes, Scientific Report FZKA-6827, March 2003. Karlsruhe, https://publikationen.bibliothek.kit.edu/270054544/3814367.
  13. A.V. Palagin, J. Stuckert, Application of the SVECHA/QUENCH Code to the Simulation of the Bundle Tests QUENCH-06 and QUENCH-12", Scientific Report FZKA-7353, December 2007. Karlsruhe, https://publikationen.bibliothek.kit.edu/270070000/3815127.
  14. S. Sadek, RELAP5/SCDAPSIM Analysis of the QUENCH-06 Experiment, FERZVNE/SA/DA-IR01/03-0, 2003.
  15. L. Sepold, et al., Experimental and Calculational Results of the QUENCH-05 Test, FZKA-6615, July 2002. https://www.semanticscholar.org/paper/Experimental-and-calculational-results-of-the-test-Sepold-Homann/0a1a87c06c9e2c835d203c3742884a229419b70c.
  16. Junghyun Yun, Taewan Kim, Jonghyun Kim, Verification of SAMG entry condition for APR1400, Ann. Nucl. Energy 75 (2015) 404-412. https://www.sciencedirect.com/science/article/pii/S0306454914004575. https://doi.org/10.1016/j.anucene.2014.08.057
  17. T.H. Vo, J.H. Song, T.W. Kim, D.H. Kim, An analysis on the severe accident progression with operator recovery actions, Nucl. Eng. Des. 280 (2014) 429-439. https://www.sciencedirect.com/science/article/pii/S0029549314005342. https://doi.org/10.1016/j.nucengdes.2014.09.023
  18. W. Hering, Ch. Homann, J.-S. Lamy, A. Miassoedov, G. Schanz, L. Sepold, M. Steinbruck, Comparison and Interpretation Report of the OECD International Standard Problem No. 45 Exercise (QUENCH-06), Scientific Report FZKA- 7353, July 2002. Karlsruhe, https://publikationen.bibliothek.kit.edu/270052469/3814240.
  19. P. Hofmann, Current knowledge on core degradation phenomena, a review, J. Nucl. Mater. 270 (1999) 194-211. https://www.sciencedirect.com/science/article/pii/S002231159800899X. https://doi.org/10.1016/S0022-3115(98)00899-X