Cavitation erosion behavior of CLAM steel weld joint in liquid lead-bismuth eutectic alloy

Lei, Yucheng; Guo, Xiaokai; Chang, Hong-xia; Li, Tianqing; Zhu, Qiang; Chen, Gang; Lu, Xiao

doi:10.1016/s1006-706x(17)30136-x

Cited by 8 publications

(3 citation statements)

References 28 publications

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“…The non-uniform microstructure with faint-sliver defects and δ-ferrite strips has been transformed into uniform lath martensite. On average, the prior austenite grains in the 0.006Y, 0.0034Y, and 0.071Y steels (measured by the linear intercept method) were sized 14.7 μm ( σ = 5.57), 11.7 μm( σ = 4.53), and 11.6 μm( σ = 2.70), respectively, much smaller than CLAM grains (20–30 μm) [17]. Zhao et al observed the grain growth in the alumina-forming austenitic steel containing 0.05 and 0.1 mass% yttrium [18].…”

Section: Resultsmentioning

confidence: 99%

Effects of yttrium on microstructure and properties of reduced activation ferritic-martensitic steel

Qiu

Zhan

et al. 2018

Materials Science and Technology

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This study investigates the inclusions, microstructure, tensile properties, and impact toughness of reduced activation ferritic/martensitic (RAFM) steels with different Y contents (0.006, 0.034 and 0.071 wt-%). Owing to the pinning of the grain boundary to the Y inclusions (which refines the original austenite grain size) and an existing Fe–Cr–Ta–Y–S–O phase, the tensile strength at both room and high temperatures increased with increasing Y content (below 0.071%). Increasing the Y content to 0.034 wt-% decreased the ductile-to-brittle transition temperature (DBTT). However, when the Y content reached 0.071 wt-%, the DBTT increased as the Y precipitated into blocky yttrium-rich inclusions. The microstructure, tensile properties, and impact toughness of the RAFM steel were optimised at a Y content of approximately 0.034 wt-%.

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Section: Resultsmentioning

confidence: 99%

Effects of yttrium on microstructure and properties of reduced activation ferritic-martensitic steel

Qiu

Zhan

et al. 2018

Materials Science and Technology

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“…It can also be found from the tables that the composition of oxide film can be divided into two layers: The outer layer is rich in Fe, Cr, and Pb (points 1 and 2), and the inner layer is rich in Fe and O (points 3 and 4), illustrating that the double-layer oxide film consisting of an Fe 3 O 4 outer layer and (Fe,Cr) 3 O 4 inner layer is formed on the steel surface during the corrosion process of the static LBE. However, this loose oxide layer is not enough to resist the penetration of lead-bismuth heavy metals, leading to corrosion of the steel [24]. Diffusion plays a crucial role in the corrosion resistance properties of coatings.…”

Section: Methodsmentioning

confidence: 99%

Influence of LBE Temperatures on the Microstructure and Properties of Crystalline and Amorphous Multiphase Ceramic Coatings

Chen

Qiu

et al. 2019

Coatings

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An Al2O3–TiO2 amorphous composite coating with a thickness of 100–120 μm was fabricated on China low activation martensitic steel (CLAM steel) by oxygen acetylene flame spraying technology and the laser in-situ reaction method. We investigated the microstructures and mechanical properties of the coating after liquid lead-bismuth eutectic (LBE) alloy corrosion under different temperatures for 300 h and found that the corrosion temperature of the LBE had no observable effect on the microstructure and chemical phase of the Al2O3–TiO2 amorphous composite coatings. However, the mechanical properties (micro-hardness and shear strength) of the Al2O3–TiO2 multiphase coating deteriorated slightly with the increase in the immersion temperature of the LBE. As a result of oxygen acetylene flame spraying and laser in-situ reaction technology, it was found that the Al2O3–TiO2 amorphous composite coating exhibits an excellent LBE corrosion resistance, which is a candidate structural material for the accelerator-driven subcritical system (ADS) to handle nuclear waste under extreme conditions.

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“…Due to the causticity of lead‐based coolant, the study of LFRs has stagnated. Recently, corrosion resistance technology has made some breakthroughs, and LFRs have reengaged widespread attention . As a result, intensive development of SMRs with heavy liquid‐metal Pb and Pb‐Bi coolants is underway.…”

Section: Introductionmentioning

confidence: 99%

Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor

et al. 2019

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Summary Lead‐based fast reactors (LFRs) have unique advantages in the development of a SMR, which has attracted a lot of attention in recent years. In this paper, an optimized design for a lead‐bismuth small modular reactor was studied on the basis of the design of SUPERSTAR. This paper aims to propose an improved LFR core scheme to enhance the neutronic performance as well as the thermal‐hydraulic safety of the reference reactor. Advanced nitride fuel is adopted in which the plutonium is used as the driven fuel, while thorium is used as the fertile fuel. Subchannel analysis was performed in the assembly design using an in‐house subchannel code, SUBAS, and an 11 × 11 scheme with a pitch‐to‐diameter (P/D) ratio of 1.4 was chosen. Using the modified assembly, the core was redesigned using the coupled code MCORE. The active core was divided into four zones with different enrichment of 239Pu to extend the core lifetime and flatten the power distribution. The main kinetic parameters and reactivity coefficients were obtained. Neutronic performance at different operation times was also studied. The maximum radial power peak factor was 1.28, while the maximum total power peak factor was 1.737. During the whole lifetime, the reactivity swing was 0.926$, which was below the limit of 1$. The subchannel study of the core flow distribution showed that a flow distributor is needed to further improve the flow distribution capability. The peaking cladding temperature was 508.7°C, and the maximum fuel center temperature was 723.4°C, both of which do not exceed the limit temperature. Compared with features of SUPERSTAR, the peaking cladding temperature was well improved and the lifetime extended.

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Cavitation erosion behavior of CLAM steel weld joint in liquid lead-bismuth eutectic alloy

Cited by 8 publications

References 28 publications

Effects of yttrium on microstructure and properties of reduced activation ferritic-martensitic steel

Effects of yttrium on microstructure and properties of reduced activation ferritic-martensitic steel

Influence of LBE Temperatures on the Microstructure and Properties of Crystalline and Amorphous Multiphase Ceramic Coatings

Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor

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