Characterisation of AlCrCuFeMo<i><sub>x</sub></i> high entropy alloys for nuclear fuel cladding

Zhu, Xiaodong; Tao, Zhenrui; Wang, Chunji; Zhang, Yanwei; Bai, Guanghai; Lan, Rui

doi:10.1080/02670836.2022.2093000

Cited by 3 publications

(1 citation statement)

References 41 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The design and preparation of new materials with excellent comprehensive properties (high strength, hardness, ductility, toughness, corrosion, oxidation, creep and wear resistance, etc.) is a long-existing concern for materials science and engineering [1][2][3]. Increasing requirements have motivated researchers to develop innovative materials with favourable performance [4].…”

Section: Introductionmentioning

confidence: 99%

Tribological behaviours of Mo–Si–B–xTi alloys against Al₂O₃ ceramic and AISI 52100 steel

Tan,

Chen,

Chen

et al. 2023

Materials Science and Technology

View full text Add to dashboard Cite

In this study, the Mo–Si–B alloys containing 10–30 wt% Ti were prepared by spark plasma sintering. The dry sliding tribological properties against Al2O3 ceramic and AISI 52100 steel were thoroughly investigated, and the corresponding wear mechanism was explored. The results indicate that the tribological properties of the MoSiBTi alloys are highly dependent on the Ti content and property of counterpart materials. The dominant wear mechanism of the MoSiBTi alloys sliding against Al2O3 ceramic is severe abrasive and adhesive wear and it transforms to mild abrasive and adhesive wear when coupled with AISI 52100 steel. It confirms that the MoSiBTi/AISI 52100 steel friction pairs show more preferable wear resistance, which is more suitable for room temperature tribological applications.

show abstract

Section: Introductionmentioning

confidence: 99%

Tribological behaviours of Mo–Si–B–xTi alloys against Al₂O₃ ceramic and AISI 52100 steel

Tan,

Chen,

Chen

et al. 2023

Materials Science and Technology

View full text Add to dashboard Cite

show abstract

Irradiation damage behavior of the non-equal atomic AlNbMoZrB high-entropy alloy

Wang,

Jiang,

Pan

et al. 2023

Progress in Natural Science: Materials International

View full text Add to dashboard Cite

Inner‐Side‐Protected Cladding with Meter Scale for High‐Temperature Oxidation Resistance via the Swaging–Drawing Process

Jo,

Choi,

Kim

et al. 2024

International Journal of Energy Research

View full text Add to dashboard Cite

Nuclear accidents, such as the Fukushima nuclear accident, have highlighted the necessity for accident‐tolerant fuel (ATF) cladding. Previous studies focused on coating the outside of Zr alloy currently used in nuclear reactors with an oxidation‐resistant material in a vacuum environment. This limits the coating to the inside of the cladding and does not tend to achieve a uniform coating on meter scale cladding. In this study, a room temperature and non‐vacuum‐based swaging–drawing process was demonstrated as an alternative cladding manufacturing process. It enables both the inner and outer sides of the 2‐m‐long Zr alloy cladding to be uniformly covered with a 100‐μm‐thick corrosion‐resistant material (316‐L stainless steel; SS316L), thereby minimizing its high‐temperature oxidation and avoiding failures. After the swaging–drawing process, there was a gap of less than 1 µm between outer SS316L and Zr alloy and a gap of about 12 µm between inner Zr alloy and SS316L. The high‐temperature oxidation properties of the resulting triplex Gachon ATF cladding tube (G‐tube) were evaluated up to 1,200°C in an atmospheric environment. Following heat treatment at 1,200°C, the control cladding completely oxidized and ruptured, potentially causing leakage of radioactive material during application. In contrast, only 15% of the G‐tube cladding manufactured by the swaging–drawing process was oxidized despite a gap, and the Zr alloy of the G‐tube changed phase from α‐Zr to α‐Zr (O) and prior β‐Zr. The cladding microstructure, oxide layer, and oxidation mechanism were analyzed through microscopy, X‐ray diffraction, and thermogravimetric analysis. As a result, it was confirmed that SS316L completely prevented oxygen diffusion into the bulk Zr alloy. In addition, there was no elemental diffusion between SS316L and the Zr alloy. These results demonstrate the feasibility of using room temperature, nonvacuum environment‐based swaging–drawing process to fabricate structurally stable ATF cladding at extremely high temperatures.

show abstract

Characterisation of AlCrCuFeMo_x high entropy alloys for nuclear fuel cladding

Cited by 3 publications

References 41 publications

Tribological behaviours of Mo–Si–B–xTi alloys against Al₂O₃ ceramic and AISI 52100 steel

Tribological behaviours of Mo–Si–B–xTi alloys against Al₂O₃ ceramic and AISI 52100 steel

Irradiation damage behavior of the non-equal atomic AlNbMoZrB high-entropy alloy

Inner‐Side‐Protected Cladding with Meter Scale for High‐Temperature Oxidation Resistance via the Swaging–Drawing Process

Contact Info

Product

Resources

About

Characterisation of AlCrCuFeMox high entropy alloys for nuclear fuel cladding

Cited by 3 publications

References 41 publications

Tribological behaviours of Mo–Si–B–xTi alloys against Al2O3 ceramic and AISI 52100 steel

Tribological behaviours of Mo–Si–B–xTi alloys against Al2O3 ceramic and AISI 52100 steel

Irradiation damage behavior of the non-equal atomic AlNbMoZrB high-entropy alloy

Inner‐Side‐Protected Cladding with Meter Scale for High‐Temperature Oxidation Resistance via the Swaging–Drawing Process

Contact Info

Product

Resources

About

Characterisation of AlCrCuFeMo_x high entropy alloys for nuclear fuel cladding

Tribological behaviours of Mo–Si–B–xTi alloys against Al₂O₃ ceramic and AISI 52100 steel

Tribological behaviours of Mo–Si–B–xTi alloys against Al₂O₃ ceramic and AISI 52100 steel