journal article·2025-05

On the degradation of Young's modulus of irradiated U-10Mo

Chaoyue Jin, Zhexiao Xie, Luning Chen, Xingdi Chen, Jing Zhang, Shurong Ding, Xiaobin Jian

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OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering

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References (50)

Show source-provided references
1. Low-temperature irradiation behavior of uranium–molybdenum alloy dispersion fuel10.1016/S0022-3115(02)00850-4 ↗
2. Irradiation behavior of atomized U–10wt.% Mo alloy aluminum skeleton dispersion fuel meat at low temperature10.1016/S0029-5493(01)00459-9 ↗
3. Fabrication of monolithic RERTR fuels by Hot isostatic pressing10.13182/NT10-A10905 ↗
4. A mesoscale stress model for irradiated U10Mo monolithic fuels based on evolution of volume fraction/radius/internal pressure of bubbles10.1016/j.net.2019.04.011 ↗
5. Craig · Mechanics of Materials · 2020
6. Summary of property-related parameters and its effect on the simulated thermo-mechanical behavior of U-10Mo monolithic fuel Plate//ASME Power Conference
7. Fission induced swelling and creep of U–Mo alloy fuel10.1016/j.jnucmat.2013.01.346 ↗
8. Mechanical properties of irradiated UMo alloy fuel10.1016/j.jnucmat.2018.12.025 ↗
9. Characterization of fission gas bubbles in irradiated U-10Mo fuel10.1016/j.matchar.2017.06.007 ↗
10. Models for effective elastic constants of irradiated U-10Mo fuels with distributed fission gas bubbles10.1016/j.jnucmat.2023.154359 ↗
11. Thermal properties of U–Mo alloys irradiated to moderate burnup and power10.1016/j.jnucmat.2015.04.040 ↗
12. Fission product induced swelling of U–Mo alloy fuel10.1016/j.jnucmat.2011.08.018 ↗
13. Correlation between Young's modulus and porosity in porous materials10.1023/A:1006669914946 ↗
14. The mechanical properties of sintered low-alloy steels10.1179/pom.1962.5.9.005 ↗
15. Anisotropic mechanical properties of porous copper fabricated by unidirectional solidification10.1016/S0921-5093(00)01402-7 ↗
16. Confirmation of theoretical relation between stiffness and porosity in ceramics10.1111/j.1151-2916.1971.tb12333.x ↗
17. Empirical dependence of elastic moduli on porosity for ceramic materials10.1111/j.1151-2916.1983.tb10051.x ↗
18. Creep, strength, expansion, and elastic moduli of sintered BeO as a function of grain size, porosity, and grain orientation10.1111/j.1151-2916.1964.tb14417.x ↗
19. Comparison of stress concentration versus minimum solid area based mechanical property-porosity relations10.1007/BF00367582 ↗
20. Expression for effect of porosity on elastic modulus of polycrystalline refractory materials, particularly aluminum oxide10.1111/j.1151-2916.1961.tb11671.x ↗
21. Treatise On Materials Science and Technology: Materials Science Series, Vol. 2. Elsevier, 2013.
22. Dependence of mechanical strength of brittle polycrystalline specimens on porosity and grain size10.1111/j.1151-2916.1959.tb13596.x ↗
23. Mechanical properties of irradiated U-10 wt.%Mo alloy degraded by porosity development10.1115/1.4064779 ↗
24. Koutský · 2013
25. Skeleton-creep based bubble growth model and multi-scale mechanical constitutive model for U-10Mo fuels under irradiation10.1016/j.ijplas.2023.103557 ↗
26. A stress-based variational model for ductile porous materials10.1016/j.ijplas.2013.10.003 ↗
27. Analytical description of an asymmetric yield function (Yoon2014) by considering anisotropic hardening under non-associated flow rule10.1016/j.ijplas.2021.102978 ↗
28. A constitutive model for plastically anisotropic solids with non-spherical voids10.1016/j.jmps.2010.03.007 ↗
29. Siefken L.J., Coryell E.W., Harvego E.A., et al. MATPRO–A library of materials properties for light-water-reactor accident analysis. Idaho Falls. 2001.
30. Modeling of irradiation-induced thermo-mechanical coupling and multi-scale behavior in a fully ceramic-microencapsulated fuel pellet10.1016/j.jnucmat.2020.152673 ↗
31. Rabin · Four-point Bend Testing of Irradiated Monolithic U-10Mo Fuel · 2015
32. Bauchau · Euler-Bernoulli Beam Theory//Structural Analysis · 2009 · 173
33. Modifications and applications of the mechanistic gaseous swelling model for UMo fuel10.1016/j.jnucmat.2014.11.065 ↗
34. Further development of the fission gas swelling model for U-10Mo fuels10.1016/j.jnucmat.2022.153769 ↗
35. Prediction and deformation mechanism analysis of high porosity in U–10Mo monolithic fuels at high burnup10.3390/met13101693 ↗
36. Shutdown-induced tensile stress in monolithic miniplates as a possible cause of plate pillowing at very high burnup10.1016/j.nucengdes.2018.01.004 ↗
37. Modeling thermal and stress behavior of the fuel–clad interface in monolithic fuel mini-plates10.1016/j.matdes.2010.02.016 ↗
38. Evaluation of U10Mo fuel plate irradiation behavior via numerical and experimental benchmarking//ASME International Mechanical Engineering Congress and Exposition
39. Marchbanks · 1995
40. Assessment of residual stresses on U10Mo alloy based monolithic mini-plates during Hot isostatic pressing10.1016/j.jnucmat.2011.08.029 ↗
41. Reymann · 1978
42. SCDAP/RELAP5/MOD 3.1 code manual: MATPRO, A library of materials properties for Light-Water-Reactor accident analysis
43. Suzuki · 2006
44. RERTR-12 insertion 1 irradiation summary
45. Perez · 2012
46. Observed changes in as-fabricated U-10Mo monolithic fuel microstructures after irradiation in the advanced test reactor10.1007/s11837-017-2564-7 ↗
47. Rice · 2015
48. The effect of the elastic modulus of the aggregate on the elastic modulus, creep and creep recovery of concrete10.1680/macr.1964.16.48.129 ↗
49. Fracture properties of an irradiated PWR UO2 fuel evaluated by micro-cantilever bending tests10.1016/j.jnucmat.2020.152209 ↗
50. On the critical mechanisms for the embrittlement and strength degradation of post-irradiated U-10Mo fuels10.1016/j.engfracmech.2024.110474 ↗