Slipcasting of MAX phase tubes for nuclear fuel cladding applications

Galvin, T.M.; Hyatt, Neil C.; Rainforth, W.M.; Reaney, Ian M.; Shepherd, D.

doi:10.1016/j.nme.2020.100725

Cited by 15 publications

(7 citation statements)

References 24 publications

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“…Recently, Ti 3 SiC 2 tubes have been processed by slip casting as a proof of concept for nuclear fuel cladding. 254 The suspension contained 49.5% dry weight basis (dwb) Ti 3 SiC 2 , 46% dwb water, 4% dwb polyethyleneimine, and 0.5% dwb. methylcellulose, and it was sintered at 1450°C for 2h under vacuum.…”

Section: Near Net Shapingmentioning

confidence: 99%

“…The green compacts were densified at 1450°C for 90 minutes using an Al 4 C 3 powder bed, achieving 95.3% relative density and a low content of impurities. Recently, Ti 3 SiC 2 tubes have been processed by slip casting as a proof of concept for nuclear fuel cladding 254 . The suspension contained 49.5% dry weight basis (dwb) Ti 3 SiC 2 , 46% dwb water, 4% dwb polyethyleneimine, and 0.5% dwb.…”

Section: Structuresmentioning

confidence: 99%

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Processing of MAX phases: From synthesis to applications

2020

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MAX phases are well-known and established due to their unique combination of properties and versatility, but this family of materials has experienced several ups and downs during its short history, including even being referred to with different names. Extensive work was carried out in the early 1960s in Vienna (Austria) by Wolfgang Jeitschko and Hans Nowotny, who discovered in more than 100 new carbides and nitrides. 1 Among them, they reported a new class of ternary systems, based on a transition metal (M), a metalloid (Me), and carbon (C), with a similar crystal structure to carbon-stabilized β-manganese phase, that is, Mo 3 Al 2 C. They were classified as "H-Phases" due to their hexagonal crystal structure, and some compositions

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Section: Near Net Shapingmentioning

confidence: 99%

Section: Structuresmentioning

confidence: 99%

Processing of MAX phases: From synthesis to applications

2020

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“…One route is to develop alternative materials, such as SiC f /SiC composites [6,10,[52][53][54][55][56], FeCrAl stainless steels [57][58][59][60][61], Mo alloys [45,[62][63][64][65], and MAX phases (the family of layered ternary compunds (M n+1 AX n ) in which M is an early transition metal, A is an A-group element and X is either carbon or nitrogen.) [51,56,[66][67][68], which can completely replace zirconium alloys. The other route is to prepare coatings on the surface of the existing zirconium alloy claddings [13,33,34,[69][70][71][72][73][74].…”

Section: Proposal and Development Of Atf Claddingmentioning

confidence: 99%

“…Mo, or Mo alloys, features an ultra-high melting point (2623 • C), excellent high-temperature strength, and high-temperature creep behavior [10,31,45]. MAX phases have a strong stiffness, good thermal conductivity, and high resistance to chemical attacks, and high-temperature oxidation [51,56,[66][67][68]. However, these new materials also have some specialproblems, such as the corrosion/dissolution of SiC that occurs under normal operating conditions of water-cooled reactors [10,46], the high tritium permeability of FeCrAl [10,46], and the high volatility of Mo under high-temperature oxidation conditions [10,45].…”

Section: Proposal and Development Of Atf Claddingmentioning

confidence: 99%

Application and Development Progress of Cr-Based Surface Coatings in Nuclear Fuel Element: I. Selection, Preparation, and Characteristics of Coating Materials

2020

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To cope with the shortcomings of nuclear fuel design exposed during the Fukushima Nuclear Accident, researchers around the world have been directing their studies towards accident-tolerant fuel (ATF), which can improve the safety of fuel elements. Among the several ATF cladding concepts, surface coatings comprise the most promising strategy to be specifically applied in engineering applications in a short period. This review presents a comprehensive introduction to the latest progress in the development of Cr-based surface coatings based on zirconium alloys. Part I of the review is a retrospective look at the application status of zirconium alloy cladding, as well as the development of ATF cladding. Following this, the review focuses on the selection process of ATF coating materials, along with the advantages and disadvantages of the current mainstream preparation methods of Cr-based coatings worldwide. Finally, the characteristics of the coatings obtained through each method are summarized according to some conventional performance evaluations or investigations of the claddings. Overall, this review can help assist readers in getting a thorough understanding of the selection principle of ATF coating materials and their preparation processes.

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“…在循环水泵表面涂刷耐磨陶瓷涂层, 可以提升叶轮的耐磨性 [14] . 三元层状可加工陶瓷材料(MAX相材料)也被认为是高温液态金属冷却快堆耐腐蚀包壳的候选材料 [10] , 同时也是新型碳化硅基材料间优异的连接材料 [15] . [16] , 用来调节燃料初期的剩余反应性, 展平功率密度, 提升燃料组件的整体燃耗 [17] .…”

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