Corrosion resistance of candidate cladding materials for supercritical water reactor

Guo, Xianglong; Yang, Fan; Gao, Wenhua; Tang, Rui; Chen, Kai; Shen, Zhao; Zhang, Lefu

doi:10.1016/j.anucene.2018.12.007

Cited by 54 publications

(27 citation statements)

References 58 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…To reduce carbon emissions, it is desirable to improve the efficiency of the steam-generating power plants by increasing the operating steam temperature and pressure, such as in the ultra-supercritical coal-fired power plants [7,8] and supercritical water-cooled nuclear reactors [9][10][11]. With the increase of operating temperatures (>600 ºC), the growth of oxide film on the F-M steels is significantly enhanced [12][13][14][15][16][17][18][19][20][21][22][23][24][25]. The consequences of the thickening and failure of the surface oxides are of increasing concern in these steam-generating power plants.…”

Section: Introductionmentioning

confidence: 99%

New insights into the oxidation mechanisms of a Ferritic-Martensitic steel in high-temperature steam

Shen

Chen

et al. 2020

Acta Materialia

Self Cite

View full text Add to dashboard Cite

The microstructure of the surface oxide film formed on an Fe-9Cr ferritic-martensitic (F-M) steel after exposure to deaerated high-temperature steam at 600 °C for 100 h has been analyzed in detail by advanced characterization techniques. The surface oxide film has been revealed to have a triplex structure, including an outer oxide layer, an inner oxide layer, and an internal oxide layer. Although the outer and inner oxide layers are continuous, the internal oxide layer has been proved to consist of interconnected metallic and chromite phases, which is a typical feature of internal oxidation. The formation mechanisms of each layer have been discussed, finding that, contrary to what the available space model suggests, an external oxidation is not the controlling oxidation mechanism of F-M steels in high-temperature steam. The higher resolution used in this study confirms that the controlling mechanism is internal oxidation.

show abstract

Section: Introductionmentioning

confidence: 99%

New insights into the oxidation mechanisms of a Ferritic-Martensitic steel in high-temperature steam

Shen

Chen

et al. 2020

Acta Materialia

Self Cite

View full text Add to dashboard Cite

show abstract

“…The continuously monitored conductivity and dissolved oxygen at the outlet of the water loop showed values below 0.2 µS/cm and 10 ppb, respectively. More details about the testing system can be found in [36][37][38][39][40][41]. The corrosion test was interrupted after 100 h and 600 h to remove several specimens from the autoclave, and the whole test was terminated after 1500 h exposure.…”

Section: Methodsmentioning

confidence: 99%

“…After exposure to 600 ºC SCW for 1500 h, the sample developed a triplex surface oxide scale (Fig. 1): a continuous outer oxide layer with high density defects (voids and cracks), underneath which is a relatively dense inner oxide layer followed by an internal oxide layer (also referred to as diffusion layer [26,33,36] or transition layer [2,28] in literature) closest to the metal matrix. The SEM-EDX results in Figs.…”

Section: Microscale Analysis: Edx and Ebsd Characterizationmentioning

confidence: 99%

Understanding the surface oxide evolution of T91 ferritic-martensitic steel in supercritical water through advanced characterization

2020

Self Cite

View full text Add to dashboard Cite

The surface oxide scale formed on T91 steel after exposure to deaerated supercritical water (SCW) at 600 ºC for 100-1500 h are characterized in detail to reveal the oxide evolution over time. A triplex structure with outer, inner and internal oxide layers has been confirmed. The thickness of each oxide layer increases with the exposure time following the power law kinetics. The different oxide phases in each oxide layer are the results of the decreasing partial pressure of oxygen inwards the depth of oxide scale. The inner and internal oxide layers are not uniform in Fe and Cr contents. The internal oxide layer consists of Cr-rich oxide precipitates surrounded by metal matrix in the grain interior, which could be explained by the internal oxidation mechanism. After a further longtime exposure, a continuous thin Cr-rich spinel oxide layer is formed at the internal oxide layer-metal matrix interface, which is the result of transition from internal to external oxidation when the outward diffusion of Cr exceeds the inward diffusion of oxygen. The inner oxide layer consists of Cr-rich spinel oxide precipitates surrounded by Fe-rich spinel oxide. The formation of the inner oxide layer is the result of further oxidation of the internal oxide layer where the metal matrix in the grain interior is oxidized into Fe-rich spinel.

show abstract

“…The most significant improvements in oxidation resistance are achieved by changing the inherent nature of the protective oxide scale. The high chromium content (> 20%) of the austenitic stainless steels results in an increased resistance [11]. Most reported results on austenitic stainless steels reveal that the surface oxide consists of a two-or three-layer structure.…”

Section: Introductionmentioning

confidence: 99%

Investigation of Oxidation Behavior of 304L and 310S Steels with Potential Application in Supercritical Water-cooled Nuclear Reactors

Galan¹,

Ducu²,

Fulger³

et al. 2020

Rev. Chim.

View full text Add to dashboard Cite

Selecting proper candidate materials is one key issue for the development of the supercritical water-cooled nuclear reactor (SCWR). Designing or choosing the most fitting materials means better sustainability, economics and safety. As the supercritical water is a very aggressive corrosive media, corrosion becomes one challenging problem for the materials used in the SCWR. This paper involves the corrosion testing of two stainless steels (304L and 310S) and microstructure evaluation of samples after being exposed to supercritical water. The test parameters were set at the temperature of 550oC and the pressure of 25 MPa for up to 63 days. The samples were investigated using gravimetric corrosion test, optical microscopy, scanning electron microscopy coupled with energy dispersive X-ray spectroscopy. Results showed a lower corrosion performance, in terms of weight change and surface oxide formation, for 304L due to its low chromium content. 310S has excellent corrosion resistance because the chromium content is higher. The results obtained will be useful in future research of test protocol and development of alloys that could be used as reactor fuel cladding and other components in the SCWR.

show abstract

Corrosion resistance of candidate cladding materials for supercritical water reactor

Cited by 54 publications

References 58 publications

New insights into the oxidation mechanisms of a Ferritic-Martensitic steel in high-temperature steam

New insights into the oxidation mechanisms of a Ferritic-Martensitic steel in high-temperature steam

Understanding the surface oxide evolution of T91 ferritic-martensitic steel in supercritical water through advanced characterization

Investigation of Oxidation Behavior of 304L and 310S Steels with Potential Application in Supercritical Water-cooled Nuclear Reactors

Contact Info

Product

Resources

About