Calibration and Validation of thermal fuel behaviour models based on the first case of the first IAEA CRP FUMEX
Source abstract
Abstract
Results of a model calibration-dedicated part of the project, entitled ‘Comprehensive Verification of the FALCON Code for Calculation of Nuclear Fuel Temperature’ are presented. For sensitivity analysis, Case 1 of the past IAEA CRP FUMEX is used. Considered are the effects caused by: correlations used for the fuel thermal conductivity; power maneuvering; fuel densification; treatment of the sinterable- and open- as-fabricated fuel porosity. An alternative correlation for fuel thermal conductivity is introduced into the code. The uncertain parameters of a few temperatures’ prediction-related models and modeling assumptions are refined. After the calibration, essentially improved agreement with the data for FUMEX Case 1 is shown. A prerequisite for the following successful verification of the advanced version of the FALCON MOD01 code as applied to fuel temperature during both steady-state- and transient- irradiation conditions is fulfilled through the current calibration.
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 (32)
Show source-provided references
1. Nuclear Fuel Safety Criteria Technical Review (second edition), ISBN 978-92-64-99178-1, OECD 2012.
2. G. Khvostov, “A dynamic model for fission gas release and gaseous swelling integrated into the FALCON fuel analysis and licensing code”, Proceedings of the TOP Fuel 2009, Paris, France, September 6-10, 2009, Paper 2085.
3. G. Khvostov, A. Romano, M.A. Zimmermann, “Modeling the effects of axial fuel relocation in the IFA-650.4 LOCA test”, Enlarged Halden Programme Group Meeting 2007, Storefjell Hotel, Gol, Norway, 11–16 March 2007, Paper F4.7.
4. 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 ↗
5. Modelling effects of transient FGR in LWR fuel rods during a LOCA10.1016/j.jnucmat.2021.153446 ↗
6. Wiesenack · 2013
7. Analysis of selected Halden overpressure tests using the FALCON code10.1016/j.nucengdes.2016.10.033 ↗
8. Models for numerical simulation of burst FGR in fuel rods under the conditions of RIA10.1016/j.nucengdes.2017.12.028 ↗
9. 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 ↗
10. Multi-scale approach to advanced fuel modelling for enhanced safety10.1016/j.pnucene.2015.03.022 ↗
11. Modeling of central void formation in LWR fuel pellets due to high-temperature restructuring10.1016/j.net.2018.07.003 ↗
12. 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 ↗
13. Verification and validation of software related to nuclear power plant instrumentation and control. IAEA Technical Report Series No. 384, 1999. Web: https://www-pub.iaea.org/mtcd/publications/pdf/trs384_scr.pdf.
14. Ferroukhi · 2019
15. The Public Domain Database on Nuclear Fuel Performance Experiments for the Purpose of Code Development and Validation. International Fuel Performance Experiments (IFPE) Database. OECD/NEA website: https://www.oecd-nea.org/jcms/pl_36360/ifpe-content (last accessed 23.06.2023).
16. Fuel modelling at extended burnup. Report of the Co-ordinated research programme on fuel modelling at extended burnup - FUMEX 1993, 1996. IAEA-TECDOC-998.
17. Fuel Modelling at Extended Burnup (FUMEX-II). Report of a Coordinated Research Project 2002, 2007. IAEA-TECDOC-1687.
18. Improvement of computer codes used for fuel behaviour simulation (FUMEX–III). Report of a coordinated research project 2008, 2012. IAEA-TECDOC-1697.
19. Analysis of thermal fuel behaviour under steady-state irradiation using selected cases of the IAEA CRP FUMEX10.1016/j.jnucmat.2023.154589 ↗
20. G. Khvostov, “Insights into fuel behaviour during relatively fast thermal transients based on calculations for two tests of the Halden IFA-507 experiment”, manuscript draft, 2023.10.1016/j.net.2023.06.045 ↗
21. G. Khvostov, “Interpretation of the online measurement data on thermal fuel behavior during the two bump-tests of the RISOE-III project”, manuscript draft, 2023.
22. EPRI License Agreement, Agreement No. 03-0601 VP, 30.09. 2004.
23. 2004
24. 2004
25. 2004
26. FALCON MOD01 update 31 with GRSW-A V4.03, Code version manual, Rev.4, 04.11. 2020.
27. G. Khvostov. Thermal physical aspects of fuel rod behavior modeling using START-3 code. IAEA Workshop on Implementation of the WWER version of the TRANSURANUS code and its application to the Safety Criteria, Sofia, Bulgaria, December 7-9, 1998. 10.13140/RG.2.2.30996.91522/1.
28. Wiesenack · Assessment of UO2 Conductivity Degradation Based on In-pile Temperature Data · 1997
29. Thermal diffusivity measurement of high BurnUp UO2 pellet irradiated at HBWR
30. Approaches to Modeling of high burn-up structure and analysis of its effects on the behaviour of light water reactor fuels in the START-3 fuel performance code
31. Analysis of cladding failure in a BWR fuel rod using a SLICE-DO model of the FALCON code10.1016/j.net.2020.05.015 ↗
32. Thermal and in-reactor densification of UO2: mechanisms and experimental results10.1016/0029-5493(78)90208-X ↗