BISON analysis of FeCrAl and Zircaloy cladding deformation during simulated BWR cyclic dryout conditions
Source abstract
Abstract
The BISON fuel performance analysis code has been used to study FeCrAl and Zircaloy cladding performance to better understand cladding deformation behavior in boiling water reactors during conditions caused by anticipated operational occurrences (AOOs) or by anticipated transients without scram (ATWS). BISON models of novel separate effects tests simulating ATWS events predicted mechanical responses to thermal cycling boundary conditions. We assessed FeCrAl and Zircaloy deformation and burst models to determine those best suited for cyclic dryout event analysis. In addition, we compared diametral strain profiles of the post-experiment claddings to simulation results. The capability of the BISON code for modeling BWR AOO or ATWS events is promising.
Source: expertdata · Quality: candidate unverified · Source record ↗
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 (37)
Show source-provided references
1. 1997
2. The BWR stability issue
3. March-Leuba · 1992
4. Costa · 2007
5. BWR stability issues in Japan10.1155/2008/358616 ↗
6. Wysocki · 2015
7. Cladding performance under power oscillations in BWRs
8. Wulff · 1990
9. Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions10.1016/j.jnucmat.2020.152256 ↗
10. W. Ma, Analysis of the OECD/NRC Oskarshamn-2 BWR stability benchmark10.1016/j.anucene.2013.09.028 ↗
11. Standard review plan, 4.2 fuel system design
12. Current status of the post boiling transition research in Japan: Integrity evaluation of nuclear fuel assemblies after boiling transition and development of rewetting correlations10.1080/18811248.2003.9715428 ↗
13. Study on dryout and rewetting during accidents including ATWS for the BWR at JAEA10.1016/j.nucengdes.2019.110164 ↗
14. Design, properties, and weldability of advanced oxidation-resistant FeCrAl alloys10.1016/j.matdes.2017.05.009 ↗
15. Steam oxidation behavior of FeCrAl cladding
16. In-situ tube burst testing and high-temperature deformation behavior of candidate materials for accident tolerant fuel cladding10.1016/j.jnucmat.2015.08.030 ↗
17. Mechanical properties of neutron-irradiated model and commercial FeCrAl alloys10.1016/j.jnucmat.2017.03.038 ↗
18. Elucidating the impact of flow on material-sensitive critical heat flux and boiling heat transfer coefficients: an experimental study with various materials10.1016/j.ijheatmasstransfer.2020.119970 ↗
19. Comparison of steady and transient flow boiling critical heat flux for FeCrAl accident tolerant fuel cladding alloy, Zircaloy, and Inconel10.1016/j.ijheatmasstransfer.2018.11.141 ↗
20. Steam oxidation, burst and critical heat flux testing of commercial FeCrAl cladding
21. Verification of the BISON fuel performance code10.1016/j.anucene.2014.03.027 ↗
22. Validating the BISON fuel performance code to integral LWR experiments10.1016/j.nucengdes.2016.02.020 ↗
23. Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: fuel modeling developments and simulation of integral experiments10.1016/j.jnucmat.2020.152645 ↗
24. Characterization of stress-rupture behavior of nuclear-grade C26M2 FeCrAl alloy for accident-tolerant fuel cladding via burst testing10.1016/j.msea.2020.139753 ↗
25. Analysis of fuel rod behavior during loss-of-coolant accidents using the BISON code: Cladding modeling developments and simulation of separate-effects experiments10.1016/j.jnucmat.2020.152537 ↗
26. Thermal creep of Zircaloy-4 cladding under internal pressure10.1080/18811248.1987.9735783 ↗
27. Erbacher · 1982 · 271
28. Experiments on ballooning in pressurized and transiently heated Zircaloy-4 tubes
29. Garzarolli · 2012
30. S. Leistikow, G. Schanz, H.V. Berg, H.V., A.E. Aly (1983). Comprehensive presentation of extended Zircaloy-4 steam oxidation results (600-1600 deg C) (IWGFPT--16). International Atomic Energy Agency (IAEA)
31. The TRANSURANUS mechanical model for large strain analysis10.1016/j.nucengdes.2014.04.041 ↗
32. Chapman · 1978 · 88
33. Williamson · 2016
34. BISON analysis of accident tolerant fuel clad concepts during normal operation and LOCA conditions
35. Thermophysical and mechanical analyses of UO2-36.4 vol% BeO fuel pellets with Zircaloy, SiC, and FeCrAl claddings10.3390/met8010065 ↗
36. The art of coupon tests10.1016/j.jcsr.2014.01.010 ↗
37. Kane · 2021