journal article·2024-11

The influence of solid solution hydrogen and precipitated hydride on the creep behavior of Zircaloy-4

Ho-A Kim, Sungjun Choi, Yong-Soo Kim, Jiwon Park, Joo-Hee Kang, Sangtae Kim

Publisher page

Abstract

The effect of hydrogen on the creep rates of Zircaloy-4 claddings especially in the low hydrogen concentration remains largely unexplored while creep is considered a main mechanism for spent nuclear fuel failure along with hydride-induced mechanisms. Here, we study the influence of hydrogen on the creep behavior of low burnup Zircaloy-4 cladding from a microstructural perspective. The creep tests at 450 °C and 120 MPa reveal that specimens with hydrogen contents below the terminal solid solubility for dissolution (TSSD) at the test temperature exhibited decreased creep resistance as hydrogen concentration increased, while those with hydrogen contents above the TSSD demonstrated increased creep resistance with higher hydrogen concentration. The lowest creep resistance occurs at the hydrogen concentration corresponding to the TSSD. Additional microstructural analyses using electron backscattered diffraction (EBSD) show the increasing intra-granular/inter-granular hydride ratio in the post-crept specimens as the hydrogen concentration decreases, suggesting that hydrogen atoms in solid solution aid creep progression. Also, an increased amount of twin boundaries is observed in post-crept specimens with hydrogen concentration above TSSD. These results suggest that creep assessment in spent nuclear fuels may require caution especially in low-burnup regime.
Source: expertdata · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · High Temperature Alloys and Creep

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

References (66)

Show source-provided references
1. B.A. Chin, M.A. Khan, J.C.L. Tarn, Deformation and fracture map methodology for predicting cladding behavior during dry storage, PNL-5998, 1986.10.2172/5162033 ↗
2. Creep deformation of an unirradiated zircaloy nuclear fuel cladding tube under dry storage conditions10.1016/0022-3115(90)90384-Y ↗
3. Wiratmo, Transitions in creep mechanisms and creep anisotropy in Zr-1Nb-1Sn-0.2Fe sheet10.1016/0029-5493(94)00960-7 ↗
4. Identifiying creep mechanisms at low stresses10.1016/S0921-5093(00)00624-9 ↗
5. Generalized creep model of Zircaloy-4 cladding tubes10.1016/S0022-3115(97)00261-4 ↗
6. Spent LWR fuel dry storage in large transport and storage casks after extended burnup10.1016/S0022-3115(97)00209-2 ↗
7. A creep damage model for initially isotropic materials with different properties in tension and compression10.1016/S0013-7944(97)00143-4 ↗
8. U.S. Nuclear regulatory commission (NRC), spent fuel project office interim staff guidance –11
9. U.S. Nuclear regulatory commission (NRC), spent fuel project office interim staff guidance –11
10. U.S. Nuclear regulatory commission (NRC), spent fuel project office interim staff guidance –11
11. Meso-scale analysis of the creep behavior of hydrogenated Zircaloy-410.1016/j.mechmat.2012.03.003 ↗
12. About the mechanisms governing the hydrogen effect on viscoplasticity of unirradiated fully annealed zircaloy-4 sheet
13. Effect of hydriding on the creep behavior of HANA-4 zirconium alloy10.1016/j.msea.2019.138435 ↗
14. Impact of hydrogen on plasticity and creep of unirradiated zircaloy-4 cladding tubes
15. Thermal creep of Zircaloy-4 tubes containing corrosion-induced hydrogen10.1016/j.jnucmat.2011.08.047 ↗
16. P. Bouffioux, S. Leclercq, C. Cappelaere, T. Bredel, Interim dry storage of pwr spent fuel assemblies: development of a long term creep law to assess the fuel cladding integrity, 2001, pp. 201–205.
17. Creep behavior of hydrogenated zirconium alloys10.1007/s11665-014-1129-y ↗
18. Effects of hydrogen on thermal creep behaviour of Zircaloy fuel cladding10.1016/j.jnucmat.2017.10.015 ↗
19. Effect of hydrogen on the creep behavior of Zr–2.5%Nb alloy at 723K10.1016/j.jnucmat.2009.01.034 ↗
20. Indentation creep study of zirconium hydrogen solid solution10.1016/j.jallcom.2004.02.035 ↗
21. A study on the initial characteristics of domestic spent nuclear fuels for long term dry storage10.5516/NET.06.2012.082 ↗
22. Influence of composition and fabrication process on out-of-pile and in-pile properties of M5 alloy
23. SISSO: a compressed-sensing method for identifying the best low-dimensional descriptor in an immensity of offered candidates
24. Zhao · 2007
25. Identification and quantification of hydride phases in Zircaloy-4 cladding using synchrotron X-ray diffraction10.1016/j.jnucmat.2009.04.004 ↗
26. Accurate prediction of threshold stress for hydride reorientation in Zircaloy-4 with directly measured interface orientation relationship
27. Intergranular δ-hydride nucleation and orientation in zirconium alloys10.1016/j.actamat.2011.07.054 ↗
28. A review of hydride precipitates in titanium and zirconium alloys: precipitation, dissolution and crystallographic orientation relationships10.1051/matecconf/202032111042 ↗
29. A. Pshenichnikov, J. Stuckert, Orientation relationships of delta hydrides in zirconium and zircaloy-4, 2016.10.1115/ICONE24-60061 ↗
30. The orientation of zirconium hydride on grain boundaries in zircaloy-210.1016/0022-3115(67)90174-2 ↗
31. Microstructure and formation mechanisms of δ-hydrides in variable grain size Zircaloy-4 studied by electron backscatter diffraction10.1016/j.actamat.2019.02.042 ↗
32. Microstructure and mechanical properties of hydride blisters formed on Zircaloy-4 claddings10.1016/j.jnucmat.2023.154777 ↗
33. The precipitation of zirconium hydride in zirconium and zircaloy-210.1016/0022-3115(72)90021-9 ↗
34. A review of factors influencing the hydride reorientation phenomena in zirconium alloy cladding during long-term dry storage
35. A phase-field model for hydride formation in polycrystalline metals: application to δ-hydride in zirconium alloys10.1016/j.actamat.2019.09.047 ↗
36. Orientation relationships between [alpha]-zirconium and [delta]-hydride within a hydride blister10.1107/S1600576717000140 ↗
37. Investigation of δ zirconium hydride morphology in a single crystal using quantitative phase field simulations supported by experiments10.1016/j.jnucmat.2021.153303 ↗
38. Microstructure and texture evolution during thermomechanical processing of β-quenched Zr10.1016/j.actamat.2014.12.033 ↗
39. Stretchability of commercial purity titanium sheet10.1007/s11661-019-05417-4 ↗
40. Microstructure evolution in cold-rolled pure titanium: modeling by the three-scale crystal plasticity approach accounting for twinning10.1007/s11661-018-4676-2 ↗
41. Tensile deformation behaviors of Zircaloy-4 alloy at ambient and elevated temperatures: in situ neutron diffraction and simulation study10.1016/j.jnucmat.2013.12.006 ↗
42. Microstructure and texture evolution in a post-dynamic recrystallized titanium during annealing, monotonic and cyclic loading10.1007/s11661-020-06071-x ↗
43. Pre-deformation enhanced {10–12} twinning in a zirconium alloy10.1016/j.msea.2020.139650 ↗
44. Chapter 14 - Continuous recrystallization during and after large strain deformation
45. Coupled quantitative modeling of microstructural evolution and plastic flow during continuous dynamic recrystallization10.1016/j.ijplas.2022.103372 ↗
46. S. Lynch, Mechanisms of hydrogen assisted cracking - a review, 2003.
47. A new model for hydrogen-assisted cracking (hydrogen “embrittlement”)10.1007/BF02642048 ↗
48. Environmentally assisted cracking: overview of evidence for an adsorption-induced localised-slip process10.1016/0001-6160(88)90113-7 ↗
49. Effects of hydrogen and carbon on thermally activated deformation in nickel10.1016/0956-7151(92)90438-K ↗
50. Hydrogen-enhanced localized plasticity—a mechanism for hydrogen-related fracture10.1016/0921-5093(94)90975-X ↗
51. Low-temperature deformation of copper single crystals10.1063/1.1722824 ↗
52. Influence of grain size and stacking-fault energy on deformation twinning in fcc metals10.1007/s11661-999-0272-9 ↗
53. Effect of grain size, dislocation cell size and deformation twin spacing on the residual strengthening of shock-loaded nickel10.1016/0025-5416(79)90172-1 ↗
54. Deformation twinning in Al-4.8 wt% Mg10.1016/0001-6160(88)90242-8 ↗
55. Hydrogen and vacancy clustering in zirconium10.1016/j.actamat.2015.09.019 ↗
56. Effect of hydrogen atom and hydrogen filled vacancies on stacking fault energy in γ-Fe by first-principles calculations10.1016/j.ijhydene.2019.04.229 ↗
57. Hydrogen influence on generalized stacking fault energies of Zr {0001} basal plane: a first-principles study10.1039/C6RA10683H ↗
58. Effect of temperature on the nano/microstructure and mechanical behavior of nanotwinned Ag films10.1007/s11661-015-3028-8 ↗
59. Vacancies, twins, and the thermal stability of ultrafine-grained copper10.1063/1.3669404 ↗
60. Anomalous deformation twinning in fcc metals at high temperatures10.1063/1.3596517 ↗
61. U.S. Nuclear Regulatory Commission (NRC), standard review plan for transportation packages for spent fuel and radioactive material, NUREG 2216, 2020.
62. A study on the effects of hydrogen content and peak temperature on threshold stress for hydride reorientation in Zircaloy-4 cladding10.1016/j.jnucmat.2018.07.005 ↗
63. Rod internal pressure of spent nuclear fuel and its effects on cladding degradation during dry storage10.1016/j.jnucmat.2017.05.047 ↗
64. Stress and temperature-dependent hydride reorientation of Zircaloy-4 cladding and its effect on the ductility degradation10.1080/00223131.2014.978829 ↗
65. Radial-hydride embrittlement of high-burnup zircaloy-4 fuel cladding10.1080/18811248.2006.9711195 ↗
66. Cladding tube deformation test for stress reorientation of hydrides10.1520/JAI101110 ↗