Measurement of the specific heat of Zr-40 wt%U metallic fuel
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- Measurement of the specific heat of Zr-40 wt%U metallic fuel
- Lee, Byung-Ho; Cheon, Jin-Sik; Koo, Yang-Hyun; Oh, Je-Yong; Yim, Jeong-Sik; Sohn, Dong-Seong; Baryshnikov, M.; Gaiduchenko, A.
- F0700; R0400; T0600; U0100
- Issue Date
- ELSEVIER SCIENCE BV
- JOURNAL OF NUCLEAR MATERIALS, v.360, no.3, pp.315 - 320
- The specific heat capacities of un-irradiated and irradiated metallic Zr-40 wt%U fuel have been measured between 50 °C and 1000 °C with a differential scanning calorimetry. The irradiated fuels have three different burnup levels of 0.38, 0.70 and 0.92 g-fission product (FP)/cm3. The measured specific heat for the un-irradiated fuel is representative and consistent with the values estimated from the Neumann-Kopp rule. The irradiated fuels exhibited a complicated behavior of the heat capacities. The unique characteristics of the specific heat capacities can be explained by the recovery of radiation damage, the formation of fission gas bubbles and fission gas release, and a phase transition in the irradiated fuels. An examination of the microstructure revealed that multiple large bubbles were formed in the irradiated fuel during specific heat measurement. The measured specific heat is expected to enable us to estimate the stored energy in the metallic fuel during certain accident scenarios and to determine the thermal conductivity of zirconium-uranium metallic fuel.
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