Corrosion issues in supercritical water reactor (SCWR) systems

Teysseyre, S.

doi:10.1533/9780857095343.6.866

Cited by 7 publications

(7 citation statements)

References 63 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Similar results were obtained in [ 12 ]. Ferritic-martensitic alloys have shown to be less susceptible to SCC.…”

Section: Introductionsupporting

confidence: 91%

“…It has been shown [ 4 , 7 , 8 , 9 , 10 , 11 , 12 ] that austenitic stainless steels, F/M steels, titanium zirconium alloys, alumina-forming austenitic (AFA) stainless steel, and oxide dispersion-strengthened (ODS) steel can be used as candidate materials for different components of SWCR. All of these materials have a number of advantages and disadvantages.…”

Section: Introductionmentioning

confidence: 99%

“…It has been shown [ 4 , 12 , 13 ] that F/M steels are highly susceptible to general corrosion, especially compared to austenitic steels. So, in [ 8 ], it was shown that after a 1500 h exposure test of T91 F/M steel in 600 °C SCW, the oxide film thickness exceeded 75 μm.…”

Section: Introductionmentioning

confidence: 99%

“…Since cracking and exfoliating of the oxide film are possible during reactor operation, F/M steels are not very suitable for fuel rod cladding with a thickness comparable to that of the oxide film. At the same time, it has been shown that F/M steels have a much higher resistance to SCC compared to austenitic steels [ 4 , 12 , 13 ]. Therefore, we consider F/M steels as a candidate material for SWCR internals with a thickness much larger than the oxide film.…”

Section: Introductionmentioning

confidence: 99%

See 3 more Smart Citations

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

et al. 2023

View full text Add to dashboard Cite

The supercritical water-cooled reactors (SWCR) belong to Generation IV of reactors. These reactors have a number of advantages over currently operating WWERs and PWRs. These advantages include higher thermal efficiency, a more simplified unit design, and the possibility of incorporating it into a closed fuel cycle. It is therefore necessary to identify candidate materials for the SWCR and validate the safety and effectiveness of their use. 12Cr ferritic–martensitic (F/M) stainless steel is considered a candidate material for SWCR internals. Radiation embrittlement and corrosion cracking in the primary circuit coolant environment are the main mechanisms of F/M steels degradation during SWCR operation. Here, the stress corrosion cracking (SCC) in supercritical water at 390 and 550 °C of 12Cr F/M steel irradiated by neutrons to 12 dpa is investigated. Autoclave tests of specially designed disk specimens in supercritical water were performed. The tests were carried out under different constant load (CL), temperature 450 °C, and pressure in autoclave 25 MPa. The threshold stress, below which the SCC initiation of irradiated 12Cr F/M steel does not occur, was determined.

show abstract

“…Similar results were obtained in [ 12 ]. Ferritic-martensitic alloys have shown to be less susceptible to SCC.…”

Section: Introductionsupporting

confidence: 91%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

et al. 2023

View full text Add to dashboard Cite

show abstract

“…According to the literature review, nickel‐base alloys exhibit the lowest weight gain of all the other kind of materials, while Alloy 800 seems to gain less weight among all the austenitic alloys . Tan et al reported very low weight gain for Alloy 800H SP tested at 500 °C and 25 MPa with a dissolved oxygen content of 25 ppb .…”

Section: Resultsmentioning

confidence: 99%

AES characterization of oxide films formed on nickel‐base alloys at Supercritical Water Reactor (SCWR) conditions

Maffiotte

Sáez-Maderuelo

Gómez-Briceño

2015

Surface & Interface Analysis

View full text Add to dashboard Cite

Austenitic alloys have shown good resistance to corrosion under light water reactor operating conditions. By this reason, these materials have been considered to be part of the new supercritical water reactor, one of the highly efficient, low waste production and simply designed Generation IV nuclear reactors. The water chemistry control and the material response to corrosion in operating conditions of the supercritical water reactor take an outstanding interest in order to minimize the release of corrosion products and their subsequent transformation into radioactive products. One nickel‐base alloy, Alloy 690TT, and one austenitic stainless steel, Alloy 800 mod, were studied under supercritical water conditions (500 °C, 25 MPa and 8 ppm of dissolved oxygen). The effect of shot‐peening surface finish was also studied on Alloy 800 mod. The corrosion rate of these alloys was evaluated by means of gravimetry. Surface analysis and subsequent depth profiles were made using Auger electron spectroscopy in order to characterize the oxide films (quantitative composition and thickness) of the different alloys as well as the influence of shot‐peening on the oxidation process. According to these results, it can be concluded that shoot‐peening favours the incorporation of chromium to the oxide layer in case of Alloy 800 mod, and the thickness of the oxide layer on Alloy 690TT is higher than on Alloy 800 mod. Copyright © 2015 John Wiley & Sons, Ltd.

show abstract

Corrosion resistance of candidate cladding materials for supercritical water reactor

Guo

Yang

Gao

et al. 2019

Annals of Nuclear Energy

View full text Add to dashboard Cite

Corrosion issues in supercritical water reactor (SCWR) systems

Cited by 7 publications

References 63 publications

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

Investigation of Stress Corrosion Cracking Resistance of Irradiated 12Cr Ferritic-Martensitic Stainless Steel in Supercritical Water Environment

AES characterization of oxide films formed on nickel‐base alloys at Supercritical Water Reactor (SCWR) conditions

Corrosion resistance of candidate cladding materials for supercritical water reactor

Contact Info

Product

Resources

About