Reaction of yttria-stabilized zirconia with zirconium, silicon and Zircaloy-4 at high temperature: A compatibility study for cermet fuels

Research output: Contribution to journalConference article

4 Citations (Scopus)

Abstract

Compatibility studies for cermet (ceramic and metal) fuels have been completed for a temperature range of 1073-1423 K. A reaction between yttria-stabilized zirconia (YSZ), as a simulated fuel, and Zr, as a candidate for a metallic matrix, has been observed at temperatures ≥1273 K, which means the formation of a metallic reaction layer at the interface between YSZ and Zr and the occurrence of metallic phases inside the YSZ. Similar results were observed for the YSZ-Zry4 (cladding) system. On the other hand, the degree of reaction was relatively large for the YSZ-Si (metallic matrix) system, and Si diffused into the YSZ. However, the maximum fuel center-line temperature can be predicted to be less than ≈1273 K for cermet fuels. Therefore, compatibility between the ceramic fuel and the metallic matrix should be good under normal reactor operational conditions. Furthermore, since the temperature of the fuel-cladding gap is lower, the cermet fuel and the cladding material are compatible.

Original languageEnglish
Pages (from-to)24-30
Number of pages7
JournalJournal of Nuclear Materials
Volume319
DOIs
Publication statusPublished - Jun 1 2003
EventProceedings of the 8th Inert Matrix Fuel Workshop - Tokai, Japan
Duration: Oct 16 2002Oct 18 2002

Fingerprint

metal fuels
Metal fuels
Yttria stabilized zirconia
Silicon
yttria-stabilized zirconia
Zirconium
compatibility
ceramics
silicon
Temperature
matrices
temperature
reactors
occurrences

All Science Journal Classification (ASJC) codes

  • Nuclear and High Energy Physics
  • Materials Science(all)
  • Nuclear Energy and Engineering

Cite this

@article{e2a4ac43523a4c67b1aeed9bbd0db78a,
title = "Reaction of yttria-stabilized zirconia with zirconium, silicon and Zircaloy-4 at high temperature: A compatibility study for cermet fuels",
abstract = "Compatibility studies for cermet (ceramic and metal) fuels have been completed for a temperature range of 1073-1423 K. A reaction between yttria-stabilized zirconia (YSZ), as a simulated fuel, and Zr, as a candidate for a metallic matrix, has been observed at temperatures ≥1273 K, which means the formation of a metallic reaction layer at the interface between YSZ and Zr and the occurrence of metallic phases inside the YSZ. Similar results were observed for the YSZ-Zry4 (cladding) system. On the other hand, the degree of reaction was relatively large for the YSZ-Si (metallic matrix) system, and Si diffused into the YSZ. However, the maximum fuel center-line temperature can be predicted to be less than ≈1273 K for cermet fuels. Therefore, compatibility between the ceramic fuel and the metallic matrix should be good under normal reactor operational conditions. Furthermore, since the temperature of the fuel-cladding gap is lower, the cermet fuel and the cladding material are compatible.",
author = "T. Arima and T. Tateyama and K. Idemitsu and Y. Inagaki",
year = "2003",
month = "6",
day = "1",
doi = "10.1016/S0022-3115(03)00129-6",
language = "English",
volume = "319",
pages = "24--30",
journal = "Journal of Nuclear Materials",
issn = "0022-3115",
publisher = "Elsevier",

}

TY - JOUR

T1 - Reaction of yttria-stabilized zirconia with zirconium, silicon and Zircaloy-4 at high temperature

T2 - A compatibility study for cermet fuels

AU - Arima, T.

AU - Tateyama, T.

AU - Idemitsu, K.

AU - Inagaki, Y.

PY - 2003/6/1

Y1 - 2003/6/1

N2 - Compatibility studies for cermet (ceramic and metal) fuels have been completed for a temperature range of 1073-1423 K. A reaction between yttria-stabilized zirconia (YSZ), as a simulated fuel, and Zr, as a candidate for a metallic matrix, has been observed at temperatures ≥1273 K, which means the formation of a metallic reaction layer at the interface between YSZ and Zr and the occurrence of metallic phases inside the YSZ. Similar results were observed for the YSZ-Zry4 (cladding) system. On the other hand, the degree of reaction was relatively large for the YSZ-Si (metallic matrix) system, and Si diffused into the YSZ. However, the maximum fuel center-line temperature can be predicted to be less than ≈1273 K for cermet fuels. Therefore, compatibility between the ceramic fuel and the metallic matrix should be good under normal reactor operational conditions. Furthermore, since the temperature of the fuel-cladding gap is lower, the cermet fuel and the cladding material are compatible.

AB - Compatibility studies for cermet (ceramic and metal) fuels have been completed for a temperature range of 1073-1423 K. A reaction between yttria-stabilized zirconia (YSZ), as a simulated fuel, and Zr, as a candidate for a metallic matrix, has been observed at temperatures ≥1273 K, which means the formation of a metallic reaction layer at the interface between YSZ and Zr and the occurrence of metallic phases inside the YSZ. Similar results were observed for the YSZ-Zry4 (cladding) system. On the other hand, the degree of reaction was relatively large for the YSZ-Si (metallic matrix) system, and Si diffused into the YSZ. However, the maximum fuel center-line temperature can be predicted to be less than ≈1273 K for cermet fuels. Therefore, compatibility between the ceramic fuel and the metallic matrix should be good under normal reactor operational conditions. Furthermore, since the temperature of the fuel-cladding gap is lower, the cermet fuel and the cladding material are compatible.

UR - http://www.scopus.com/inward/record.url?scp=0038696371&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=0038696371&partnerID=8YFLogxK

U2 - 10.1016/S0022-3115(03)00129-6

DO - 10.1016/S0022-3115(03)00129-6

M3 - Conference article

AN - SCOPUS:0038696371

VL - 319

SP - 24

EP - 30

JO - Journal of Nuclear Materials

JF - Journal of Nuclear Materials

SN - 0022-3115

ER -