Mandrel diameter effect on ring-pull testing of nuclear fuel cladding
Source abstract
Abstract
Inconsistencies in ring-pull testing methods for thin-walled tubes make it difficult to compare a material's mechanical properties in the hoop direction presented in past publications. The effect of test setup, specifically mandrel diameter, was investigated for nuclear fuel cladding tubes of the iron-chromium-aluminum (FeCrAl) alloy, C26M (Fe-12Cr-6Al-2Mo). Mandrel diameter for ring-pull testing can change how the ring deforms and friction effects, further convoluting the results from testing. To address the impact of mandrel size in relation to ring diameter, gaugeless ring-pull samples were tested across a range of mandrel diameters and compared to uniaxial tensile tests from the same tube of material. Two groups of samples were tested: an as-received, low ductility sample set and an annealed, high ductility sample set, both cut from the same extruded tube. By pairing systematic variation of mandrel geometry with analysis of local strain gradients using digital image correlation, this study investigates the effect of test fixture geometry on apparent mechanical properties and effective strain fields and provides guidance for comparing previously published data. Certain features in uniaxial stress-strain curves (namely the yield strength, ultimate tensile strength, and uniform elongation) appeared to have analogies in the effective stress-strain curves from ring-pull testing. These corresponding features are compared to expose biases in the analysis of material properties using gaugeless ring-pull and to provide novel guidance on test setup during experimental design.
Source: openalex_inverted_index · Quality: baseline
Research context
OpenAlex topics: Nuclear Materials and Properties · High Temperature Alloys and Creep · Fusion materials and technologies
SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.
References (48)
Show source-provided references
1. The issue of stress state during mechanical tests to assess cladding performance during a reactivity-initiated accident (RIA)10.1016/j.jnucmat.2011.03.015 ↗
2. Burst behavior of nuclear grade FeCrAl and Zircaloy-2 fuel cladding under simulated cyclic dryout conditions10.1016/j.jnucmat.2020.152256 ↗
3. Strength and rupture geometry of un-irradiated C26M FeCrAl under LOCA burst testing conditions10.1016/j.jnucmat.2021.153242 ↗
4. Multiaxial plastic deformation of Zircaloy-4 nuclear fuel cladding tubes
5. Evaluation of axial and tangential ultimate tensile strength of zirconium cladding tubes10.1016/j.net.2018.01.002 ↗
6. Microstructure and texture evolution and ring-tensile properties of recrystallized FeCrAl ODS cladding tubes
7. ASTM International, Standard test method for flexural strength of advanced ceramics at ambient temperature, ASTM C1161-13, Annual Book of ASTM Standards, ASTM International, West Conshohocken, PA, United States, 2013, doi:10.1520/C1161-18R23.1.
8. Reproducing hoop stress-strain behavior for tubular material using lateral compression test10.1016/S0020-7403(03)00115-2 ↗
9. Mechanical response of oxidized Zircaloy-4 cladding material submitted to a ring compression test10.1016/j.jnucmat.2008.10.027 ↗
10. Evaluation of the true-strength characteristics for isotropic materials using ring tensile test10.1016/j.net.2021.01.033 ↗
11. Characterization of IASCC crack tips extracted from neutron-irradiated flux thimble tube specimens in view of a probabilistic fracture model10.1016/j.jnucmat.2022.154015 ↗
12. Advanced techniques for mechanical testing of irradiated cladding materials
13. Development of cone-wedge-ring-expansion test to evaluate the tensile HOOP properties of nuclear fuel cladding10.1016/j.pnucene.2018.06.015 ↗
14. Investigation of the C-ring test for measuring hoop tensile strength of nuclear grade ceramic composites10.1016/j.jnucmat.2014.05.002 ↗
15. Hyde, T.H.; Hyde, C.J.; Sun, W., Theoretical basis and practical aspects of small specimen creep testing. J. Strain Anal. Eng. Des. 48(2) (2012) 112–125 10.1177/0309324712463299.10.1177/0309324712463299 ↗
16. The development of a novel technique for small ring specimen tensile testing10.1016/j.tafmec.2018.11.016 ↗
17. Yegorova · 1999 · Vol. 2
18. Youssef · 2018
19. Development of axial and ring hoop tension testing methods for nuclear fuel cladding tubes
20. A correlation-based approach for evaluating mechanical properties of nuclear fuel cladding tubes10.1016/j.jnucmat.2022.154192 ↗
21. A new approach to measuring transverse properties of structural tubing by a ring test - experimental investigation10.1520/JTE11966J ↗
22. Failure of Zircaloy cladding under transverse plane-strain deformation10.1016/S0029-5493(98)00284-2 ↗
23. Microstructure and mechanical properties of ferritic/martensitic steel EP-823 after neutron irradiation to high doses in BOR-6010.1016/j.jnucmat.2004.04.310 ↗
24. Mechanical properties and microstructure of three Russian ferritic/martensitic steels irradiated in BN-350 reactor to 50 dpa at 490°C10.1016/j.jnucmat.2007.03.161 ↗
25. Low-temperature mechanical properties of Fe-0.06C-18Cr-10Ni-0.4Ti austenitic steel determined using ring-pull tensile tests and microhardness measurements10.1016/j.jnucmat.2007.03.052 ↗
26. Severe embrittlement of neutron irradiated austenitic steels arising from high void swelling10.1016/j.jnucmat.2008.12.077 ↗
27. Improved evaluation of ring tensile test ductility applied to neutron irradiated 42XNM tubes in the temperature range of (500–1100) °C10.1016/j.net.2019.11.019 ↗
28. The Estimation of Taylor-Quinney coefficients using small ring specimens10.1007/s11340-022-00920-z ↗
29. Material selection for accident tolerant fuel cladding
30. Gigax · 2018
31. Characterization of stress-rupture behavior of nuclear-grade C26M2 FeCrAl alloy for accident-tolerant fuel cladding via burst testing10.1016/j.msea.2020.139753 ↗
32. Yamamoto, Y.; Sun, Z., Quality optimization of commercial FeCrAl tube production, Oak Ridge National Laboratory. Oak Ridge, TN, United States, 2017 Ornl/Tm-2017/338 doi:10.2172/2311323.10.2172/2311323 ↗
33. Hayne · 2022
34. Beck · 2022
35. M.N. Gussev, J.T. Busby, K.G. Field, M.A. Sokolov, S.E. Gray, Role of scale factor during tensile testing of small specimens, Small Specimen Test Techniques: 6th Volume, ASTM International, 2015, pp. 3149, doi:10.1520/STP157620140013.10.1520/STP157620140013 ↗
36. Sub-size tensile specimen design for in-reactor irradiation and post-irradiation testing10.1016/j.nucengdes.2017.06.008 ↗
37. 2016
38. Grain size estimation in anisotropic materials10.1007/s11661-998-0176-0 ↗
39. STM Internatnional, Standard test methods for determining average grain size. ASTM E112-10, Annual Book of ASTM Standards, ASTM Internatnional, West ConShohocken, PA, (2010), doi:10.1520/E0112-13R21.1.4.
40. The deformation and ageing of mild steel: III Discussion of results10.1088/0370-1301/64/9/303 ↗
41. Microstructural control of FeCrAl alloys using Mo and Nb additions10.1016/j.matchar.2017.08.008 ↗
42. Meyers · 2009
43. Frisch-Fay · 1962
44. The bending of a thin rod having initially uniform curvature10.1016/0020-7403(63)90049-3 ↗
45. Fichter · 1989
46. Stiffness of a curved beam subjected to axial load and large displacements10.1016/j.ijsolstr.2004.08.018 ↗
47. Large deflections of a clamped-slider-pinned rod with uniform intrinsic curvature10.1016/j.ijsolstr.2017.09.006 ↗
48. Budynas · 2015