2010
DOI: 10.1016/j.jnucmat.2010.04.004
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FCCI barrier performance of electroplated Cr for metallic fuel

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Cited by 32 publications
(9 citation statements)
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“…In the case of the U-10Zr/T92 specimen, the migration phenomena of U, Zr, Fe, and Cr as well as the Nd lanthanide fission products were observed at the eutectic melting region. The measured penetration 5.6 at.% (U-19Pu-10Zr) [2] 11.1 at.% (U-19Pu-10Zr) [2] 2.44 at.% (U-10Zr): in this work Unirradiated U-10Zr [18][19][20]   …”
Section: Discussionmentioning
confidence: 51%
See 1 more Smart Citation
“…In the case of the U-10Zr/T92 specimen, the migration phenomena of U, Zr, Fe, and Cr as well as the Nd lanthanide fission products were observed at the eutectic melting region. The measured penetration 5.6 at.% (U-19Pu-10Zr) [2] 11.1 at.% (U-19Pu-10Zr) [2] 2.44 at.% (U-10Zr): in this work Unirradiated U-10Zr [18][19][20]   …”
Section: Discussionmentioning
confidence: 51%
“…These results are presented in Figure 7 along with the experimental results of the penetration rate with 1 h heating data in the FBTA tests which were reported in the literature [2,3]. In addition, the measured eutectic penetration rates for the unirradiated U-10Zr fuel slug with FMS (ferritic martensitic steel, HT9 or Gr.91) cladding specimens through the out-of-pile heating test which are available in the literature [18][19][20] are also presented in Figure 7. In the case of the heating test for unirradiated fuel with HT9 at 700 • C during 96 h, the measured penetration depth along the cladding direction was approximately 8 µm (penetration rate = 2.3 × 10 −5 µms −1 Figure 13, the measured eutectic penetration rates for the irradiated fuel specimens are higher than those for the unirradiated U-10Zr specimen.…”
Section: Results Of Irradiated Fuel After High-temperature Heating Testmentioning
confidence: 78%
“…Since then, the FCCI issue has been significantly improved by alloying the fuels with Zr or Pd elements [11], applying a physical diffusion barrier between fuel and cladding, and employing advanced ferritic/martensitic claddings. Chromium, as one of the major alloying elements in advanced cladding steels, has been consistently showing a beneficial effect on improving the FCCI [6,12]. Cr is not expected to form eutectic phases with lanthanides (or actinides) around the operating temperature between 450C and 650C of a fast reactor [13].…”
Section: Introductionmentioning
confidence: 99%
“…Fission product lanthanides are known to be a major cause of FCCI in fast reactors. Although several methods, such as coatings or foil barriers have been tested [1][2][3][4][5], an alternative is proposed whereby an additive dopant is used to chemically bind the lanthanides as intermetallic compounds. This study provides evidence that palladium-neodymium intermetallic compounds, in direct contact with iron, will mitigate this interaction.…”
Section: Introductionmentioning
confidence: 99%