Impact of PSI-KIT Nitriding model on hypothetical Spent Fuel Pool accident simulation
2
조회
0
다운로드
0
인용
0
참고문헌
키워드
초록
In past years the Paul Scherrer Institute (PSI, Switzerland) and the Karlsruhe Institue of Technology (KIT, Germany)) collaborated to develop a model to account for the active role of nitrogen in the air oxidation of a Zircalloy cladding. The “PSI-KIT Nitriding Model for Zirconium based Fuel Cladding” model was implemented at PSI into PSI-MELCOR 1.8.6. In order to make a preliminary evaluation of the effect of the new model on the evolution of full-scale spent fuel pool accidents, one spent fuel pool event was analyzed using the PSI research version of PSIMELCOR 1.8.6, which includes the nitriding model. To adapt an existing input deck for the calculations, a sensitivity study was conducted to find an optimal nodalization for the analyses. The nitriding model results were compared to those calculated with the MELCOR 1.8.6-PSI without the new nitriding model. The results demonstrate the effect of the nitriding reactions in spent fuel pool accident progression. Moreover, they confirm the impact of ZrN formation during cladding oxidation in air when the oxidation reactions lead to oxygen starvation inside the fuel assemblies. The nitriding reaction led to higher chemical heat generation during the accident and to an earlier failure of the cladding than when the effect of nitrogen reactions was not considered. It should be noted that the nitriding model, as implemented in the PSI version of MELCOR 1.8.6 has not yet been conclusively validated. Thereby the results presented in this paper should be treated as a preliminary demonstration of the capabilities of the model.
Abstract
In past years the Paul Scherrer Institute (PSI, Switzerland) and the Karlsruhe Institue of Technology (KIT, Germany)) collaborated to develop a model to account for the active role of nitrogen in the air oxidation of a Zircalloy cladding. The “PSI-KIT Nitriding Model for Zirconium based Fuel Cladding” model was implemented at PSI into PSI-MELCOR 1.8.6. In order to make a preliminary evaluation of the effect of the new model on the evolution of full-scale spent fuel pool accidents, one spent fuel pool event was analyzed using the PSI research version of PSIMELCOR 1.8.6, which includes the nitriding model. To adapt an existing input deck for the calculations, a sensitivity study was conducted to find an optimal nodalization for the analyses. The nitriding model results were compared to those calculated with the MELCOR 1.8.6-PSI without the new nitriding model. The results demonstrate the effect of the nitriding reactions in spent fuel pool accident progression. Moreover, they confirm the impact of ZrN formation during cladding oxidation in air when the oxidation reactions lead to oxygen starvation inside the fuel assemblies. The nitriding reaction led to higher chemical heat generation during the accident and to an earlier failure of the cladding than when the effect of nitrogen reactions was not considered. It should be noted that the nitriding model, as implemented in the PSI version of MELCOR 1.8.6 has not yet been conclusively validated. Thereby the results presented in this paper should be treated as a preliminary demonstration of the capabilities of the model.
참고문헌 (26)
- Jonathan Birchley, "Simulation of air oxidation during a reactor accident sequence: Part 1 – Phenomenology and model development", Annals of Nuclear Energy, 40(1), pp.163~170 (2012), Elsevier BV[DOI]
- Spent Fuel Pool Project Phase II, "S. G. Durbin", U.S. NRC, ~, pp.NUREG (2016), CR-7216
- Martin Steinbrueck, "Oxidation of Zircaloy-4 in steam-nitrogen mixtures at 600–1200 °C", Journal of Nuclear Materials, 490, pp.226~237 (2017), Elsevier BV[DOI]
- M. Lasserre, "Qualitative analysis of Zircaloy‐4 cladding air degradation in O<sub>2<", sub>–N<sub>2<, Materials and Corrosion, pp.2013, 65(3)[DOI]
- Nitriding and Re-oxidation Behavior of Zircaloy-4 at High Temperatures, "Sanggil Park", ~, pp.Dissertation ETH No. 27146 (2020)
- S. Park, "Current understanding of hightemperature oxidation phenomena during air ingress scenarios", Proceedings of the 10th European Review Meeting on Severe Accident Research (2022)
- Martin Steinbrück, "Prototypical experiments relating to air oxidation of Zircaloy-4 at high temperatures", Journal of Nuclear Materials, 392(3), pp.531~544 (2009), Elsevier BV[DOI]
- C. Duriez, "Reaction in air and in nitrogen of pre-oxidised Zircaloy-4 and M5™ claddings", Journal of Nuclear Materials, 441(1-3), pp.84~95 (2013), Elsevier BV[DOI]
- J. Birchley, "First assessment of PSI nitriding model against QUENCHair experiments", Proceedings of the 27th International QUENCH Workshop (2022), Karlsruhe Institute of Technology
- B.S. Jackel, "Development of a Computer Code Model for Nitriding and Re-Oxidation of Cladding Materials Under Severe Accident Conditions", International Conference Nuclear Energy For New Europe (2018)
- B.S. Jackel, "Application of a Newly Developed Computer Code Model for Nitriding and Re-oxidation of Cladding Materials on Separate Effect Tests and Integral Experiments", the 9TH European Review Meeting on Severe Accident Research (ERMSAR2019) (2019)
- Code Assessment Programme for MELCOR1.8.6, Contribution to HSK 2007 Annual Research and Experience Report e Erfahrungs-Und Forschungsbericht, "T. Haste", ~, pp.HSK-AN-6502 (2007)
- Jonathan Birchley, "First assessment of PSI nitriding model against QUENCH-air experiments", Proceedings, 27th International QUENCH Workshop (2022), Karlsruhe Institute of Technology
- E. Beuzet, "Cladding oxidation during air ingress. Part II: Synthesis of modelling results", Annals of Nuclear Energy, 93, pp.18~27 (2016), Elsevier BV[DOI]
- A. Wielenberg, "Recent improvements in the system code package AC2 2019 for the safety analysis of nuclear reactors", Nuclear Engineering and Design, 354, pp.110211~ (2019), Elsevier BV[DOI]
- M.F. Haurais, "Evaluate the contribution of the fuel cladding oxidation process on the hydrogen production from the reflooding during a potential severe accident in a nuclear reactor", PhD, pp.2016
- O. Coindreau, "Severe accident code-to-code comparison for two accident scenarios in a spent fuel pool", Annals of Nuclear Energy, 120, pp.880~887 (2018), Elsevier BV[DOI]
- B. Jackel, "EMUG Presentation: the Role of Nitrogen in Spent Fuel Pool Accident Scenarios", 7th EMUG (2015)
- E. T. Hayes, "Some Effects of Heating Zirconium in Air, Oxygen, and Nitrogen", Journal of The Electrochemical Society, 96(3), pp.142~ (1949), The Electrochemical Society[DOI]
- Phenomena Identification and Ranking Table, , Nuclear Energy Agency, Organisation for Economic Co-operation and Development, OECD, ~, pp.NEA No. 7443 (2018)
- Kwang-Il Ahn, "An assessment of radiological source terms for loss of cooling and coolant accidents of a PWR spent fuel pool", Progress in Nuclear Energy, 129, pp.103513~ (2020), Elsevier BV[DOI]
- Jonathan C. Birchley, "Preliminary interpretative analysis of the QUENCH-18 bundle test using SCDAPSim", mod3.5, 2019, pp.130, 20~33[DOI]
- J. Stuckert, "Experimental results of the QUENCH-16 bundle test on air ingress", Progress in Nuclear Energy, 71, pp.134~141 (2014), Elsevier BV[DOI]
- Juri Stuckert, "Experimental and modelling results of the QUENCH-18 bundle experiment on air ingress, cladding melting and aerosol release", Nuclear Engineering and Design, 379, pp.111267~ (2021), Elsevier BV[DOI]
- P. Vryashkova, "Improving the results of QUENCH-16 experiment by using new models of MELCOR 2.1", BgNS TRANSACTIONS, 22(1), pp.26~29 (2017)
- Róbert Farkas, "Effect of steam and oxygen starvation on severe accident progression with air ingress", Nuclear Engineering and Design, 396, pp.111884~ (2022), Elsevier BV[DOI]
