Modelling effects of transient FGR in LWR fuel rods during a LOCA
Source abstract
Abstract
Outcomes of an activity on development and verification of models for Fission Gas Release in Light-Water Reactor fuels during Loss-of-Coolant Accidents are described. The GRSW-A model of the FALCON code is extended to simulate the processes of fuel fragmentation and concomitant transient Fission Gas Release. The FRELAX code is redesigned with a view to simulation of bulk flow and diffusion of the gases in the rod free volume. Finally, close coupling of the updated FALCON and FRELAX codes is set up, referred to as the F2F coupled code system, due to which the two codes are being exchanging data during their simultaneous analysis. Three Halden LOCA experiments, IFA-650.12/13/14, using fuel irradiated in the Swiss Leibstadt NPP to a high level of fuel burnup are analyzed with the F2F coupled code system. Overall, the results of calculation for the selected three tests of the IFA-650 series are in good agreement, or conservative in comparison to the data.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Nuclear Materials and Properties · Nuclear reactor physics and engineering · Nuclear Engineering Thermal-Hydraulics
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (43)
Show source-provided references
1. W. Wiesenack, T. Fuketa, C. Grandjean, H. Hozer, S. Kelppe, G. Khvostov, B. Hafidi, L. Heins, F. Nagase, M. Petit, B. Therache, M. Valach, J. Voglewede, Safety Significance of the Halden IFA-650 LOCA Test Results, NEA/CSNI/R(2010)5, OECD-NEA-CSNI, Paris, France, 2010, web: https://www.oecd-nea.org/jcms/pl_18942.
2. B.C. Oberländer, W. Wiesenack, Overview of Halden LOCA experiments (with emphasis on fuel fragmentation) and plans, Institutt for Energiteknikk, IFE/KR/E-2014/001, 2017. Available at http://hdl.handle.net/11250/2598322.
3. W. Wiesenack, Summary and Comparison of LOCA Tests with BWR Fuel in the Halden Reactor Project Test Series IFA-650, HPR-383, 2015.
4. A model for fission gas release and gaseous swelling of the uranium dioxide fuel coupled with the FALCON code10.1016/j.nucengdes.2011.06.020 ↗
5. Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA10.1016/j.nucengdes.2017.12.028 ↗
6. Analytical criteria for fuel fragmentation and burst FGR during a LOCA10.1016/j.net.2020.03.009 ↗
7. Modeling the effects of axial fuel relocation in the IFA-650.4 LOCA test
8. Some insights into the role of axial gas flow in fuel rod behaviour during the LOCA based on Halden tests and calculations with the FALCON-PSI code10.1016/j.nucengdes.2011.03.003 ↗
9. International Atomic Energy Agency (1994), Water reactor fuel element modelling at high burnup and its experimental support (FUMEX), IAEA-TECDOC-957, 1994.
10. International Atomic Energy Agency (2012), Fuel Modelling at Extended Burnup (FUMEX-II), IAEA-TECDOC-1687, 2012.
11. International Atomic Energy Agency (2013), Improvement of Computer Codes Used for Fuel Behaviour Simulation (FUMEX-III), IAEA-TECDOC-1697, 2013.
12. FALCON code-based analysis of PWR fuel rod behaviour during RIA transients versus new U.S.NRC and current Swiss failure limits10.1016/j.net.2021.06.001 ↗
13. EPRI Product Id 1011307 (2004), Fuel analysis and licensing Code: FALCON MOD01: Volume 1: Theoretical and Numerical Bases, 2004, web: https://www.epri.com/#/pages/product/000000000001011307/.
14. EPRI License Agreement, Agreement No. 03-0601 VP, 30.09.2004.
15. Analysis of Halden LOCA test with the BWR high burnup fuel
16. Brankov · 2017
17. L.O. Jernkvist, Computational assessment of LOCA simulation tests on high burnup fuel rods in Halden and Studsvik, SSM report 2017:12, ISSN: 2000-0456, 2017. Available at www.stralsakerhetsmyndigheten.se.
18. A. Bianco, Experimental investigation on the causes for pellet fragmentation under LOCA conditions, Thesis/Dissertation, Technische Univ. Muenchen (Germany), Fakultaet fuer Maschinenwesen, 2015. Available at https://inis.iaea.org/search/search.aspx?orig_q=RN:47001455.10.1016/j.jnucmat.2015.05.035 ↗
19. The Dynamic Model of Grain Boundary Processes in High Burn-up LWR Fuel and its Application in Analysis by the START-3 Code
20. Analysis of effects of pellet-cladding bonding on trapping of the released fission gases in high-burnup KKL BWR fuels10.1016/j.nucengdes.2016.06.021 ↗
21. Formation of pellet-cladding bonding layer in high burnup BWR fuels10.1080/18811248.1997.9733726 ↗
22. Analysis of mechanical load on cladding induced by fuel swelling during power ramp in high burn-up rod by fuel performance code FEMAXI-610.1016/j.nucengdes.2003.11.017 ↗
23. Mechanistic model for the fragmentation of the high-burnup structure during LOCA10.1016/j.jnucmat.2015.08.015 ↗
24. Е.М. Яворский, А.А. Детлаф, Справочник по физике, изд. «НАУКА», с. 211, Москва, 1974.
25. Collision diameters of some gases as functions of temperature
26. OECD/NEA-CSNI (2009), Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions. State-of-the-art Report, OECD report (NEA No.6846), ISBN 978-92-64-99091-3, 2009.
27. G. Khvostov, Special modelling: LOCA and RIA, OECD – HRP Summer School, Lecture, 2013.
28. R.S. Brokaw, Viscosity of gas mixtures, NASA Technical Note, NASA-NT-D4496, 1968, web: https://ntrs.nasa.gov/citations/19680012255.
29. Engineering ToolBox (2014), Gases - Dynamic Viscosity, [online] Available at: https://www.engineeringtoolbox.com/gases-absolute-dynamic-viscosity-d_1888.html [Accessed 24 April 2019].
30. Jernkvist · 2020
31. K. Wegner, Mass Transfer – Estimation of Diffusivities, ETH Zurich 2017, K. Wegner Lecture 8, 08.11.2017.
32. van Heijningen · 1967
33. Diffusion in mixture of ideal gases
34. Multi-scale approach to advanced fuel modelling for enhanced safety10.1016/j.pnucene.2015.03.022 ↗
35. EPRI Product Id 1011309 (2004), Fuel analysis and licensing Code: FALCON MOD01: volume 3: code verification, Electric Power Research Institute, 2004, web: https://www.epri.com/#/pages/product/000000000001011309/.
36. A three-dimensional axial fuel relocation framework with discrete element method to support burnup extension10.1016/j.jnucmat.2020.152408 ↗
37. K. Radhakrishnan, A. C. Hindmarsh, Description and Use of LSODE, the Livermore Solver for Ordinary Differential Equations, NASA Relevance Publication 1327, Lawrence Livermore National Laboratory Report UCRL-ID-113855, 1993, web: https://ntrs.nasa.gov/citations/19940030753.10.2172/15013302 ↗
38. Rod Overpressure/Lift-off Testing at Halden In-pile Data and Analysis10.1080/18811248.2006.9711193 ↗
39. Review of Halden reactor project high burnup fuel data that can be used in safety analyses10.1016/S0029-5493(97)00056-3 ↗
40. Braten · 1999
41. Characterization of High Burnup Fuel for Safety Related Fuel Testing10.1080/18811248.2006.9711189 ↗
42. G. Ledergerber et al., Fuel Performance Beyond Design – Exploring the Limits, 2010 LWR Fuel Performance /Top Fuel / WRFPM, Paper 0044, 2010.
43. EPRI Product Id 1011308 (2004), Fuel analysis and licensing Code: FALCON MOD01: volume 2: code user's guide, Electric Power Research Institute, 2004, web: https://www.epri.com/#/pages/product/000000000001011308/.