K. Minato et al., FISSION-PRODUCT RELEASE FROM ZRC-COATED FUEL-PARTICLES DURING POSTIRRADIATION HEATING AT 1800 AND 2000-DEGREES-C, Journal of nuclear materials, 249(2-3), 1997, pp. 142-149
Citations number
26
Categorie Soggetti
Nuclear Sciences & Tecnology","Mining & Mineral Processing","Material Science
The ZrC coating layer is a candidate to replace the SiC coating layer
of the Triso-coated fuel particles for high-temperature gas-cooled rea
ctors. Post-irradiation heating tests of the ZrC-Triso coated UO2 part
icles were performed at 1800 degrees C for 3000 h and at 2000 degrees
C for 100 h to study the release behavior of fission products. The fis
sion gas release monitoring and the X-ray microradiography revealed th
at no through-coating failure occurred during the heating tests. The h
igh cesium retention of the ZrC-Triso coated fuel particles was confir
med up to 1800 degrees C. The diffusion coefficient for cesium in the
ZrC layer was more than two orders smaller than that in the SiC layer
at 1800 degrees C. The diffusion coefficient for ruthenium in the ZrC
layer was almost the same as that for cesium in the SiC layer. (C) 199
7 Elsevier Science B.V.