Research progress in microstructure and service performance of high-strength and corrosion-resistant ODS?FeCrAl alloy
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摘要: 氧化物彌散強化（Oxide dispersion strengthened，ODS）FeCrAl合金由于加入一定量的Al元素，使合金表面可形成一層薄而致密的Al2O3保護膜，使得合金即便在1400 ℃的水蒸汽下也不會因為腐蝕導致失效。同時，大量超細氧化物粒子的彌散強化作用使其具備優異的高溫強度。這種兼具高溫強度和耐腐蝕的特性使得ODS?FeCrAl合金成為非常有前景的事故容錯燃料（Accident tolerant fuel , ATF）包殼候選材料，也是快堆等其他工作于高溫強腐蝕環境的先進反應堆包殼的重要候選材料。Al元素的引入會使ODS鐵基合金中彌散粒子的種類發生變化，進而影響其顯微組織和力學性能。針對ODS?FeCrAl合金中引入Al元素所導致的顯微組織變化及其對蠕變性能的影響，總結了國內外相關研究進展，旨在為適用于先進反應堆的ODS?FeCrAl合金的發展提供參考。Abstract: The demand for cleaner and more efficient new generation reactors has become increasingly urgent to solve the world’s energy supply and environmental issues such as carbon emissions. The Fukushima nuclear power plant disaster in 2011 prompted researchers to pay more attention to the safety performance of cladding tube materials in nuclear power plants under non-working conditions. Earlier, zirconium alloy, which was widely used in cladding tube materials, would cause serious accidents due to the production of explosive products after failure under the condition of beyond design-basis accident (BDBA). To avoid this problem, researchers proposed the design concept of accident tolerant fuel (ATF). ATF requires the new cladding material to retain a particular strength under the condition of BDBA and does not produce explosive products, thereby avoiding catastrophic accidents. Oxide dispersion strengthened (ODS)?FeCrAl alloy has good high-temperature strength due to its dispersion strengthening. After treatment, the presence of Al forms a thin and dense Al2O3 protective film on the surface of the alloy. This layer of Al2O3 protects the alloy, ensuring that it does not fail due to corrosion even when exposed to 1400 °C steam. This combination of high-temperature strength and corrosion resistance makes ODS?FeCrAl alloy a promising candidate for advanced reactor cladding materials like ATF. Although the introduction of aluminum improves the corrosion resistance of the alloy, it also changes the type of dispersed particles in the ODS alloy. The size of dispersed particles containing Al is usually larger than before, and their number density decrease. The state of dispersed particles in the alloy is closely related to the mechanical properties of the alloy. In this paper, the current research progress is summarized using relevant domestic and foreign documents considering the influence and control method of the microstructure of ODS?FeCrAl alloy due to the introduction of the Al element with the goal of serving as a reference for the forture development of ODS?FeCrAl alloy.
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Key words:
- accident tolerant fuel /
- ODS stell /
- microstructure /
- corrosion resistance /
- creep performance
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圖 2 各種先進核能系統中關鍵材料的服役環境[32]
VHTR—very high temperature reactor; SCWR—supercritical water reactor; GFR—gas-cooled fast reactor; LFR—lead-cooled fast reactor; MSR—molten salt reactor; SFR—sodium-cooled fast reactor; TWR—traveling ware reactor
Figure 2. The service environment of core materials in various advanced nuclear energy systems[32]
圖 3 Y/Ti 比與彌散粒子尺寸的關系.（a）9Cr 無 Ti 樣品 TEM 照片;（b）9Cr 0.1Y/Ti 樣品 TEM 照片; （c） 9Cr 0.4 Y/Ti 樣品 TEM 照片; （d）9Cr 1.0 Y/Ti 樣品 TEM 照片; （e）9Cr 不同 Y/Ti 比樣品的納米顆粒尺寸 分布;（f）MA957 中顆粒尺寸與化學成分的關系[46?47]
Figure 3. Relationship between Y/Ti ratio and dispersed particle size: (a) TEM graph of 9Cr without Ti sample; (b) TEM graph of 9Cr 0.1Y/Ti sample; (c) TEM graph of 9Cr 0.4 Y/Ti sample; (d) TEM graph of 9Cr 1.0 Y/Ti sample; (e) 9Cr nanoparticle size distribution of samples with different Y/Ti ratios; (f) correlation between particle size and chemical composition in MA957[46?47]
圖 4 不同稀土氧化物對 ODS?FeCr 微觀結構與力學性能的關系。（a）14Cr?Y2O3 TEM 照片；（b）14Cr?Y2O3 彌散顆粒分布統計；（c）14Cr?La2O3 TEM 照片；（d）14Cr?La2O3樣品彌散顆粒分布統計；（e）14Cr?CeO2 TEM 照片；（f）14Cr?CeO2彌散顆粒分布統計；（g）14Cr?Y2O3，14Cr?La2O3和 14Cr?CeO2晶粒尺寸分布；（h） 14Cr?Y2O3，14Cr?La2O3和 14Cr?CeO2樣品的實驗與計算屈服應力[48]
σp—Strengthening due to the nanoscale oxides; σGB—Strengthening due to the Hall-Petch effect; σM—Matrix yield stress; σExp—Experiment yield stress; σ0.2—Yield stress
Figure 4. Relationship between different rare earth oxides on the microstructure and mechanical properties of ODS?FeCr: (a)TEM graph of 14Cr?Y2O3; (b) particle size distribution of 14Cr?Y2O3; (c) TEM graph of 14Cr?La2O3; (d) particle size distribution of 14Cr?La2O3; (e)TEM graph of 14Cr?CeO2; (f) particle size distribution of 14Cr?CeO2; (g) grain size distribution of 14Cr?Y2O3, 14Cr?La2O3, and 14Cr?CeO2; (h)experimental and calculated yield stress of 14Cr?Y2O3, 14Cr?La2O3, and 14Cr?CeO2 samples[48]
圖 9 同成分 ODS 合金與非 ODS 化合金的蠕變閾值應力示意圖[74?75]
Figure 9. Schematic of creep threshold stress of the same composition ODS alloy and non-ODS alloy[74?75]
εss—Steady-state uniaxial strain rate; k—Boltzmann constant; T—Temperature; Dsd—Lattice self-diffusion coefficient; G—Shearmodulus; b—Burgers vector; σss—Uniaxial steady-state stress.
表 1 圖 12 中各樣品彌散顆粒統計結果及應力閾值計算值[81]
Table 1. The statistical results of the dispersed particles of each sample and calculated value of the stress threshold in Fig. 12[81]
Sample λ/m Is/m rs/m D/m σth/MPa YAl specimen 1.48×10?7 1.26×10?7 4.40×10?9 8.31×10?9 97?132 YTi specimen 9.30×10?8 8.21×10?8 4.70×10?9 8.54×10?9 156?212 YZr specimen 1.02×10?7 8.96×10?8 4.90×10?9 8.94×10?9 145?195 Note: λ—Inter-particle distance; Is—Center-particle distance; rs—Average particle radius; D—Harmonic parameter; σth—Threshold stress of dislocation creep. 
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