DEVELOPMENT OF A NOVEL STRUCTURAL MATERIAL (SIMP STEEL) FOR NUCLEAR EQUIPMENT WITH BALANCED RESIS-TANCES TO HIGH TEMPERATURE, RADIATION AND LIQUID METAL CORROSION

doi:10.11900/0412.1961.2016.00320

Acta Metall Sin

2016, Vol. 52

Issue (10): 1207-1221 DOI: 10.11900/0412.1961.2016.00320

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DEVELOPMENT OF A NOVEL STRUCTURAL MATERIAL (SIMP STEEL) FOR NUCLEAR EQUIPMENT WITH BALANCED RESIS-TANCES TO HIGH TEMPERATURE, RADIATION AND LIQUID METAL CORROSION

Ke YANG¹(

),Wei YAN¹,Zhiguang WANG²,Yiyin SHAN¹,Quanqiang SHI¹,Xianbo SHI¹,Wei WANG¹

1 Institute of Metal Research, Chinese Academy of Sciences, Shenyang 110016, China
2 Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China

Cite this article:

Ke YANG, Wei YAN, Zhiguang WANG, Yiyin SHAN, Quanqiang SHI, Xianbo SHI, Wei WANG. DEVELOPMENT OF A NOVEL STRUCTURAL MATERIAL (SIMP STEEL) FOR NUCLEAR EQUIPMENT WITH BALANCED RESIS-TANCES TO HIGH TEMPERATURE, RADIATION AND LIQUID METAL CORROSION. Acta Metall Sin, 2016, 52(10): 1207-1221.

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Abstract

Accelerator driven subcritical (ADS) system has been recognized to be the most promising technology for safely treating the nuclear wastes by now. In China, ADS system has achieved great progress in both fundamental research and engineering practice. This system is composed of three parts, which are accelerator, spallation target and reactor. The biggest challenge exists in the structural material for the spallation target is to possess not only good heat-resistance and radiation resistance but also a resistance to liquid metal corrosion. A novel martensitic heat-resistant steel, SIMP steel, has been developed against this challenge. By negotiating the effects of the contents of those important elements such as C, Cr and Si in the (9%~12%)Cr martensitic heat-resistant steel on heat resistance, radiation resistance, and liquid metal corrosion resistance, an optimized chemical composition was obtained for SIMP steel and a good balance was reached among these three properties. The test results conducted on 1 t and 5 t grade SIMP steels showed that this novel steel is much potential as a candidate structural material for the spallation target in ADS system.

Key words: ADS system steel for nuclear structure heat-resistant radiation liquid metal corrosion

Received: 20 July 2016

ZTFLH:

Fund: Supported by Strategic Priority Research Program of Chinese Academy of Sciences (Nos.XDA03010301 and XDA03010302)

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	Ke YANG
	Wei YAN
	Zhiguang WANG
	Yiyin SHAN
	Quanqiang SHI
	Xianbo SHI
	Wei WANG

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https://www.ams.org.cn/EN/10.11900/0412.1961.2016.00320 OR https://www.ams.org.cn/EN/Y2016/V52/I10/1207

Fig.1 Principle for chemical composition design of SIMP steel (LBE—Pb-Bi eutectic)

Fig.2 SIMP steel ingots of different grades

Table 1 Chemical compositions of 1 t and 5 t grade SIMP steels (mass fraction / %)

Table 2 Contents of active elements in the 5 t grade SIMP steel (mass fraction / %)

Fig.3 OM (a) and TEM (b) images of martensitic microstructures of the as-treated SIMP steel

Table 3 Mechanical properties of SIMP steels on 1 t and 5 t grade steels and T91 steel

Fig.4 Comparisions of creep strength between 1 t SIMP steel and T91 steel at 550 ℃ (a), 600 ℃ (b) and 650 ℃ (c)

Fig.5 Comparisions of creep strength between 5 t SIMP steel and T91 at 400 ℃ (a), 450 ℃ (b), 600 ℃ (c), 700 ℃ (d) and 750 ℃ (e)

Fig.6 SEM images of 1 t SIMP steel aged at 650 ℃ for 120 h (a) and 2400 h (b)

Fig.7 Weight increase (a) and increasing rate (b) of SIMP steel and P92 steel oxidized at 700 ℃

Fig.8 Weight increase (a) and increasing rate (b) of SIMP steel and P92 steel oxidized at 800 ℃

Fig.9 Cross section SEM images of oxidation films on SIMP steel (a) and T91 steel (b) oxidized at 700 ℃ for 500 h

Fig.10 XRD spectra of the oxidation films on SIMP steel (a) and T91 steel (b) oxidized at 700 ℃ for 500 h

Fig.11 Cross section SEM images of SIMP (a, c, e) and T91 (b, d, f) steels after exposures in static oxygen-saturated liquid LBE alloy at 600 ℃ for 100 h (a, b), 500 h (c, d) and 1000 h (e, f) (IOZ—internal oxidation zone)

Fig.12 Thicknesses of oxide film (a) and diffusion layer (b) obtained by oxidations of SIMP and T91 steels in static oxygen-saturated liquid LBE alloy at 600 ℃ (K—parabolic constant)

Fig.13 EPMA element distributions of SIMP (a) and T91 (b) steels after exposure in static oxygen-saturated liquid LBE alloy at 600 ℃ for 1000 h

Fig.14 EPMA element distributions of Fe-Cr spinel and diffusion layers on SIMP (a) and T91 (b) steels after exposures in the static oxygen-saturated liquid LBE alloy at 600 ℃ for 1000 h (Zones A and B indicate Cr segregation and Cr even zones, respectively)

Fig.15 Binding strength test between the oxidation film and the steel matrix

Fig.16 Room temperature tensile properties of SIMP steel and T91 steel after soaking in the oxygen-staturated liquid LBE at 600 ℃ for different times
(a) strength (b) ductility

Fig.17 600 ℃ tensile properties of SIMP (a~c) and T91 (d~f) steels after soaking in the oxygen-saturated LBE at 600 ℃

Table 4 Diameter change in the gauge section of tensile samples after soaking in liquid LBE alloy for different times (mm)

Fig.18 Tensile properties of as-treated SIMP steel in liquid LBE at 300 ℃

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