Oxidation at high temperatures in steam atmosphere and quench of silicon carbide composites for nuclear application

Avincola, Valentina Angelici; Große, M.; Stegmaier, U.; Steinbrueck, Martin; Seifert, H. J.

doi:10.1016/j.nucengdes.2015.10.002

Cited by 55 publications

(12 citation statements)

References 37 publications

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“…hermo 2021, 1, FOR PEER REVIEW 12 from 1400 °C to 2000 °C [46], which correspond very well to the results obtained with smaller CVD-SiC samples in the LAHF facility. According to the gas release data (Figure 12b), which are a measure for the oxidation kinetics, a protective silica scale should have formed immediately after start of steam injection.…”

Section: Quench-sr Facilitysupporting

confidence: 84%

“…A number of experiments with SiC f -SiC ceramic-matrix composite (CMC) cladding tubes from various manufactures have been conducted already with this facility. Figure 12 provides, as one example, results of a transient test with such a cladding tube segment from 1400 • C to 2000 • C [46], which correspond very well to the results obtained with smaller CVD-SiC samples in the LAHF facility. According to the gas release data (Figure 12b), which are a measure for the oxidation kinetics, a protective silica scale should have formed immediately after start of steam injection.…”

Section: Quench-sr Facilitysupporting

confidence: 73%

“…Steam oxidation tests at temperatures above 1600 • C are very challenging as major refractory lining materials, such as alumina and even zirconia, in conventional test facilities are at their limits. In recent years, several efforts have been made to modify existing or to develop new test facilities [46,47] to study SiC under extreme conditions. To perform the oxidation tests at temperatures higher than 1600 • C, the QUENCH-SR facility with utilization of induction heating was developed at Karlsruhe Institute of Technology [55].…”

Section: Advanced Test Facilities For Atf-claddingsmentioning

confidence: 99%

“…To perform the oxidation tests at temperatures higher than 1600 • C, the QUENCH-SR facility with utilization of induction heating was developed at Karlsruhe Institute of Technology [55]. First oxidation and quench tests of SiC at temperatures up to 2000 • C in steam atmosphere were reported by Avincola et al [46]. Under the same motivation, JAEA has also developed a new test facility (Laser Heating Facility: LAHF) with utilization of laser heating for oxidation tests at extreme temperatures [47].…”

Section: Advanced Test Facilities For Atf-claddingsmentioning

confidence: 99%

“…For metallic samples, the heating power is directly produced in the sample. SiC samples, however, are filled with graphite (used as a susceptor for the HF inductive heating purpose [46]) and tightly sealed with end caps at both sides to avoid interaction of the graphite with the oxidizing steam atmosphere. This heating method results in uniform and prototypical heat generation for cladding tube samples as in fuel rods, where the heat is also produced by the UO 2 fuel within the cladding.…”

Section: Quench-sr Facilitymentioning

confidence: 99%

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Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview

Pham

Kurata

Steinbrueck

2021

Thermo

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Since the nuclear accident at Fukushima Daiichi Nuclear Power Station in 2011, a considerable number of studies have been conducted to develop accident tolerant fuel (ATF) claddings for safety enhancement of light water reactors. Among many potential ATF claddings, silicon carbide is one of the most promising candidates with many superior features suitable for nuclear applications. In spite of many potential benefits of SiC cladding, there are some concerns over the oxidation/corrosion resistance of the cladding, especially at extreme temperatures (up to 2000 °C) in severe accidents. However, the study of SiC steam oxidation in conventional test facilities in water vapor atmospheres at temperatures above 1600 °C is very challenging. In recent years, several efforts have been made to modify existing or to develop new advanced test facilities to perform material oxidation tests in steam environments typical of severe accident conditions. In this article, the authors outline the features of SiC oxidation/corrosion at high temperatures, as well as the developments of advanced test facilities in their laboratories, and, finally, give some of the current advances in understanding based on recent data obtained from those advanced test facilities.

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Section: Quench-sr Facilitysupporting

confidence: 84%

Section: Quench-sr Facilitysupporting

confidence: 73%

Section: Advanced Test Facilities For Atf-claddingsmentioning

confidence: 99%

Section: Advanced Test Facilities For Atf-claddingsmentioning

confidence: 99%

Section: Quench-sr Facilitymentioning

confidence: 99%

See 3 more Smart Citations

Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview

Pham

Kurata

Steinbrueck

2021

Thermo

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Tantalum Oxidation in Steam Atmosphere

et al. 2015

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An Overview of Mechanisms of the Degradation of Promising ATF Cladding Materials During Oxidation at High Temperatures

Steinbrueck,

Grosse,

Tang

et al. 2024

High Temperature Corrosion of mater.

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Accident tolerant fuel (ATF) cladding is a new type of nuclear fuel cladding designed to improve the safety and performance of nuclear reactors. In this paper, the kinetics and degradation mechanisms during high-temperature oxidation in steam of the three most promising ATF cladding materials, i.e., chromium-coated zirconium alloys, FeCrAl alloys, and silicon carbide-based composites, are described. Each system has its own degradation mechanisms leading to different maximum survival temperatures. After providing general information and data to understand the oxidation and degradation processes, illustrative examples obtained at the Karlsruhe Institute of Technology are given for each type of cladding. The maximum temperatures at which the barrier effect of the cladding can be maintained for a reasonable period of time during nuclear accident scenarios are 1200–1300 °C for Cr-coated Zr alloys, 1400 °C for FeCrAl alloys, and 1700 °C for SiC-based composite claddings.

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Oxidation at high temperatures in steam atmosphere and quench of silicon carbide composites for nuclear application

Cited by 55 publications

References 37 publications

Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview

Steam Oxidation of Silicon Carbide at High Temperatures for the Application as Accident Tolerant Fuel Cladding, an Overview

Tantalum Oxidation in Steam Atmosphere

An Overview of Mechanisms of the Degradation of Promising ATF Cladding Materials During Oxidation at High Temperatures

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