Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors

Jiang, Gedong; Xu, Donghai; Feng, Peng; Guo, Shuhai; Yang, Jianqiao; Li, Yanhui

doi:10.1016/j.jallcom.2021.159235

Cited by 62 publications

(8 citation statements)

References 150 publications

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“…Our investigation aims to enhance the FRAPCON code's physical characteristics to perform advanced simulations based on the material properties library [6]. This research is critical for developing more efficient and safer nuclear fuel systems, and zircaloy cladding is an essential element for standard fuel systems.…”

Section: Methodsmentioning

confidence: 99%

Uranium nitride and silicide composite fuels used to reduce fuel oxidation

Gomes

2024

JER

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Section: Methodsmentioning

confidence: 99%

Uranium nitride and silicide composite fuels used to reduce fuel oxidation

Gomes

2024

JER

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“…Besides the work conducted at GE, ORNL, and at NFD, the FeCrAl alloys have also been tested in China and other countries but not in a highly systematic manner. A review article by Jiang et al [18] listed the double layer oxides formed under BWR NWC (with Besides the work conducted at GE, ORNL, and at NFD, the FeCrAl alloys have also been tested in China and other countries but not in a highly systematic manner. A review article by Jiang et al [18] listed the double layer oxides formed under BWR NWC (with dissolved oxygen) on FeCrAl coupons.…”

Section: Matrix Matrixmentioning

confidence: 99%

“…A review article by Jiang et al [18] listed the double layer oxides formed under BWR NWC (with Besides the work conducted at GE, ORNL, and at NFD, the FeCrAl alloys have also been tested in China and other countries but not in a highly systematic manner. A review article by Jiang et al [18] listed the double layer oxides formed under BWR NWC (with dissolved oxygen) on FeCrAl coupons. They reported that the external layer was an Fe-rich spinel sometimes containing nickel (Ni) (Ni is not present in FeCrAl alloys but may still be present in the test water because of minor dissolution from the stainless steel piping and autoclave body).…”

Section: Matrix Matrixmentioning

confidence: 99%

Distinctive Oxide Films Develop on the Surface of FeCrAl as the Environment Changes for Nuclear Fuel Cladding

Qu,

Yin,

Larsen

et al. 2024

CMD

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The corrosion-resistant properties of IronChromium–Aluminum (FeCrAl) alloys have been known for nearly a century. Since the 1950s, they have been explored for application in the generation of nuclear power. In the last decade, the focus has been on the use of FeCrAl as cladding for uranium dioxide fuel in light water reactors (LWRs). The corrosion resistance of this alloy depends on the oxide that it can develop on the surface. In LWRs in the vicinity of 300 °C, the external surface oxide of the FeCrAl cladding could be rich in Fe under oxidizing conditions but rich in Cr under reducing conditions. If there is an accident and the cladding is exposed to superheated steam, the cladding will protect itself by developing an alpha aluminum film on the surface.

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“…Material kelongsong bahan bakar nuklir yang biasa digunakan yaitu zircaloy. Paduan ini memiliki penampang penangkapan neutron termal yang rendah, ketahanan korosi yang sangat baik, dan sifat mekanik yang memadai pada temperatur tinggi [5].…”

Section: Pendahuluanunclassified

“…Paduan Zircaloy-4 memiliki penampang lintang serapan neutron yang mirip dengan zirkonium, yaitu sebesar 0,22 barns [16] sebagai material kelongsong bahan bakar pada reaktor nuklir komersial [17]. Paduan Zircaloy-4 banyak digunakan sebagai komponen pada reaktor yang dimoderasi oleh air karena penampang serapan lintang neutron yang rendah, ketahanan yang tinggi terhadap korosi uap dan air, dan sifat mekanik yang baik.…”

Section: Sifat Dan Ciri Paduan Zircaloy-4unclassified

STUDI PENGARUH PENAMBAHAN YTTRIUM DAN PERLAKUAN PANAS BETA TERHADAP KETAHANAN HIDROGEN PADUAN ZIRCALOY-4-0,1%Mo PADA TEMPERATUR 600°C DAN 800°C

Alfatar

Basuki

Prajitno

2022

urania

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STUDI PENGARUH PENAMBAHAN YTTRIUM DAN PERLAKUAN PANAS BETA TERHADAP KETAHANAN HIDROGEN PADUAN ZIRCALOY-4-0,1%Mo PADA TEMPERATUR 600°C DAN 800°C. Energi listrik merupakan sumber energi yang banyak digunakan dan dibutuhkan oleh manusia. Sehingga kebutuhan energi listrik ini akan meningkat seiring bertambahnya jumlah populasi manusia. Pembangkit Listrik Tenaga Nuklir (PLTN) merupakan salah satu solusi dari persoalan tersebut. Salah satu komponen penting reaktor nuklir yaitu kelongsong bakar nuklir biasanya menggunakan material berupa paduan zirkonium, namun penggunaan paduan ini dalam waktu yang lama akan rentan terhadap penggetasan akibat penetrasi hidrogen. Serangkaian percobaan dilakukan untuk mengetahui pengaruh penambahan yttrium dan perlakuan panas beta terhadap ketahanan hidrogen dan sifat mekanis paduan Zircaloy-4-0,1%Mo-xY (x=0 wt%; 0,5 wt%; 1 wt%). Penambahan yttrium menyebabkan peningkatan jumlah presipitat yang diduga adalah α-Y sekaligus meningkatkan kekerasan paduan baik pada paduan as cast maupun perlakuan panas beta. Perlakuan panas beta menurunkan kekerasan paduan akibat peningkatan jumlah fasa β-Zr. Peningkatan ketahanan hidrogen dapat dilakukan dengan penambahan yttrium karena bertindak sebagai penstabil fasa β-Zr. Sama halnya dengan perlakuan panas beta yang dapat meningkatkan ketahanan hidrogen dengan metode yang sama yaitu meningkatkan jumlah fasa β-Zr sehingga jumlah hidrogen yang dapat larut meningkat. Penambahan 1 wt% Y pada paduan zircaloy-4-0.1%Mo dengan perlakuan panas beta menunjukkan ketahanan hidrogen yang paling baik dengan ketebalan 6,24 μm pada temperatur 600°C dan 545,5 μm pada temperatur 800°C.Kata kunci: Zircaloy-4, ketahanan hidrogen, variasi yttrium

show abstract

Corrosion of FeCrAl alloys used as fuel cladding in nuclear reactors

Cited by 62 publications

References 150 publications

Uranium nitride and silicide composite fuels used to reduce fuel oxidation

Uranium nitride and silicide composite fuels used to reduce fuel oxidation

Distinctive Oxide Films Develop on the Surface of FeCrAl as the Environment Changes for Nuclear Fuel Cladding

STUDI PENGARUH PENAMBAHAN YTTRIUM DAN PERLAKUAN PANAS BETA TERHADAP KETAHANAN HIDROGEN PADUAN ZIRCALOY-4-0,1%Mo PADA TEMPERATUR 600°C DAN 800°C

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