2006
DOI: 10.1016/j.jnucmat.2006.02.067
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Yttrium stabilised zirconia inert matrix fuel irradiation at an international research reactor

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Cited by 14 publications
(8 citation statements)
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“…The Z2 fuel showed similar level of the FP gas release with UO 2 fuel at similar volumetric fission density and temperature. Streit et al investigated the irradiation behavior of YSZ based fuel (IMF-ATT in IFA-651) [8]. The FGR also found to be comparable to what would be expected Fig.…”
Section: Fractional Fission-gas Releasementioning
confidence: 74%
See 1 more Smart Citation
“…The Z2 fuel showed similar level of the FP gas release with UO 2 fuel at similar volumetric fission density and temperature. Streit et al investigated the irradiation behavior of YSZ based fuel (IMF-ATT in IFA-651) [8]. The FGR also found to be comparable to what would be expected Fig.…”
Section: Fractional Fission-gas Releasementioning
confidence: 74%
“…Recently, irradiation tests on inert matrix fuels (IMF) have been carried out by several groups, with the object to study the transmutation of americium and/or the incineration of plutonium [7][8][9]. The comparison is also made with the results of the latter IMF irradiation experiments.…”
Section: Introductionmentioning
confidence: 99%
“…IFE performed also the destructive (ceramography) and nondestructive post irradiation examinations [13]. The results of the first examinations are published in [9,10,13]. A neighbouring rod piece was sent to PSI for density, ICP-MS and electron microprobe analyses (EPMA).…”
Section: Materials Specification and Irradiationmentioning
confidence: 99%
“…The aim of this experiment in the Material Test Reactor was to measure the thermal behaviour of an yttria stabilised zirconia inert matrix fuel under irradiation conditions similar to current LWRs and to compare the performance with MOX rods [9][10][11]. The present work focuses the post irradiation examination on the change in the fuel microstructure that has occurred during irradiation and the redistribution of the main constituents including the burning of plutonium as well as the behaviour of some fission products.…”
Section: Introductionmentioning
confidence: 99%
“…Pouchon et al [3] have calculated the solubility limit of Cs to be 1.5 at.% at 2000 K, whereas Wang et al [4] have estimated that the defective implanted matrix could accept a higher concentration of Cs up to 8 at.% at room temperature. Nevertheless, the inner operating temperature of inert matrix fuels in reactors is likely to reach 1900 K [5,6]. In those conditions Cs diffusion, release and/ or precipitation are expected.…”
Section: Introductionmentioning
confidence: 99%