journal article·2023-11Open access

The deformation and burst behavior of Zircaloy-4 cladding tubes with hydride rim features subject to internal pressure loads

David Kamerman

Abstract

No abstract is available for this record. The assistant can identify its topic from the title, but cannot infer the study’s results.

Source: Not provided · Quality: missing

Research context

OpenAlex topics: Nuclear Materials and Properties · Nuclear and radioactivity studies · Nuclear reactor physics and engineering

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (32)

Show source-provided references
1. Clifford · 2015
2. Fujishiro, T., P. E. MacDonald , R. L. Johnson, and R. K. McCardell, 1978. “Light Water Reactor Fuel Response During Reactivity Initiated Accident Experiments.” NUREG/CR-0269 TREE 1237, Idaho National Engineering Laboratory, Idaho Falls, ID. https://inis.iaea.org/search/search.aspx?orig_q=RN:10437309.10.2172/6891041 ↗
3. McCardell, R. K., and P. E. MacDonald. 1980. “Safety and licensing issues that are being addressed by the Power Burst Facility test programs.” In proceedings from CSNI Specialist Meeting on Safety Aspects of Fuel Behavior in Off-Normal and Accident Conditions, Helsinki Finland. https://inis.iaea.org/collection/NCLCollectionStore/_Public/12/581/12581573.pdf?r=1.
4. Jensen, C. B., N. E. Woolstenhulme, and D. M. Wachs. 2018. “The TREAT Experiment Legacy Supporting LWR Fuel Technology.” In proceedings of TopFuel 2018 Prague, CZ. https://www.euronuclear.org/archiv/topfuel2018/fullpapers/TopFuel2018-A0168-fullpaper.pdf.
5. Summary and Interpretation of the CABRI REP-Na Program10.13182/NT07-A3815 ↗
6. Thresholds for failure of high-burnup LWR fuels by Pellet Cladding mechanical interaction under reactivity-initiated accident conditions10.1080/00223131.2019.1637795 ↗
7. Transient Response of LWR Fuels (RIA)
8. NEA. 2010. “Nuclear Fuel Behavior under Reactivity-initiated Accident Conditions.” NEA No. 6847. Organization for Economic Co-operation and Development. https://www.oecd-nea.org/jcms/pl_14526/nuclear-fuel-behaviour-under-reactivity-initiated-accident-ria-conditions?details=true.
9. Radiation Effects in Zirconium Alloys
10. Corrosion of Zirconium Alloys10.1016/B978-0-08-056033-5.00063-X ↗
11. IAEA. 2006. “Thermophysical Properties Database of Materials for Light Water Reactors and Heavy Water Reactors.” IAEA-TECDOC-1496. https://www.iaea.org/publications/7489/thermophysical-properties-database-of-materials-for-light-water-reactors-and-heavy-water-reactors.
12. D. Kamerman, C. Jensen, C. Folsom, N. Woolstenhulme, and D. Wachs. 2022. “A review of cladding failure thresholds in RIA conditions based on transient reactor test data and the need for continued testing.” In proceedings from Topfuel 2022, Raleigh, NC. https://www.ans.org/meetings/topfuel2022/session/view-1381/.10.13182/TopFuel22-38944 ↗
13. “On the Embrittlement of Zircaloy-4 Under RIA Relevant Conditions” In Zirconium in the Nuclear Industry: Thirteenth International Symposium
14. Fracture of Zircaloy-4 cladding tubes with or without hydride blisters in uniaxial to plane strain conditions with standard and optimized expansion due to compression tests10.1016/j.msea.2014.02.075 ↗
15. Investigation of Hydride Rim Effect on Failure of Zircaloy-4 Cladding with Tube Burst Test10.1080/18811248.2005.9726364 ↗
16. Fuel cladding behavior under rapid loading conditions10.1016/j.jnucmat.2015.11.032 ↗
17. Revisiting the method to obtain the mechanical properties of hydrided fuel cladding in the hoop direction10.1016/j.jnucmat.2012.06.003 ↗
18. Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes
19. Expansion deformation behavior of zirconium alloy claddings with different hydrogen concentrations10.1016/j.jnucmat.2021.153082 ↗
20. Formation and characterization of hydride rim structures in Zircaloy-4 nuclear fuel cladding tubes10.1016/j.jnucmat.2023.154675 ↗
21. Multiaxial Plastic Deformation of Zircaloy-4 Nuclear Fuel Cladding Tubes10.1080/00295450.2022.2160174 ↗
22. Cracking and spalling of the oxide layer developed in high-burnup Zircaloy-4 cladding under normal operating conditions in a PWR10.1016/j.jnucmat.2018.10.003 ↗
23. Stress biaxiality in high-burnup PWR fuel cladding under reactivity-initiated accident conditions10.1080/00223131.2013.787030 ↗
24. Deformation behavior of recrystallized and stress-relieved Zircaloy-4 fuel cladding under biaxial stress conditions10.1080/00223131.2017.1383213 ↗
25. Crack growth in the through-thickness direction of hydrided thin-wall Zircaloy sheet10.1016/j.jnucmat.2011.09.005 ↗
26. Nanoindentation measurements of the mechanical properties of zirconium matrix and hydrides in unirradiated pre-hydrided nuclear fuel cladding10.1016/j.jnucmat.2014.04.045 ↗
27. Some Observations on the deformation characteristics of bulk polycrystalline zirconium hydrides; Part 1 The deformation and fracture of hydrides based on the δ-phase10.1007/BF00550212 ↗
28. Mechanical properties of zirconium, titanium, and yttrium hydride alloys10.1007/BF01529980 ↗
29. Determination of fracture strength of δ-zirconium hydrides embedded in zirconium matrix at high temperatures10.1016/j.jnucmat.2012.12.045 ↗
30. Deformation mechanism of embedded hydride within the polycrystalline zirconium matrix10.1016/j.jnucmat.2022.153736 ↗
31. T. Sugiyama, M. Umeda, H. Sasajima, M. Suzuki, T. Fuketa, Effect of Initial Coolant Temperature on Mechanical Fuel Failure under Reactivity-Initiated Accident Conditions, Proceedings of Top Fuel 2009, Paris France.10.1016/j.anucene.2008.12.003 ↗
32. Evaluation of Initial Temperature Effect on Transient Fuel Behavior under Simulated Reactivity-Initiated Accident Conditions10.1080/18811248.2010.9711634 ↗