Determination of melting point of mixed-oxide fuel irradiated in fast breeder reactor.

Tachibana, Toshimichi; Ohmori, Tsuyoshi; Yamanouchi, Sadamu; Itaki, Toshiyuki

doi:10.3327/jnst.22.155

Cited by 12 publications

(8 citation statements)

References 5 publications

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“…Fig. 5 compares the melting point of UO 2 observed in previous studies [6,7,9,12,[20][21][22][23][24][25][26]. The melting point of UO 2.00 observed in the present work was 3128 ± 35 K which is in good agreement with the average of those earlier works.…”

Section: Discussionsupporting

confidence: 95%

Solidus and liquidus of plutonium and uranium mixed oxide

Kato

Morimoto

Sugata³

et al. 2008

Journal of Alloys and Compounds

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Section: Discussionsupporting

confidence: 95%

Solidus and liquidus of plutonium and uranium mixed oxide

Kato

Morimoto

Sugata³

et al. 2008

Journal of Alloys and Compounds

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“…For comparison, Tables 2 and 3 give the measured temperatures and as-fabricated compositions of a JOYO Mk-I core fuel reported by Tachibana et al 4) and on fuel irradiated in Rapsodie reported by Komatsu et al 5) In both tables, the effects brought to fuel composition and O/M ratio have been evaluated as in Table 1 by the ORIGEN-2 code and by linear increasing O/M ratio model.…”

Section: Methodsmentioning

confidence: 99%

Melting Temperature of Mixed Oxide Fuels for Fast Reactors.

Konno

Hirosawa²

2002

J. Nucl. Sci. Technol.

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Alternation of the melting temperature of irradiated mixed oxide (MOX) fuel in fast reactors with progress of burnup was determined in relation to the actinide fractions contained and of the oxygen-to-metal (O/M) ratio. Based on ideal solution models of UO 2 -PuO 2 and UO 2 -PuO 2 -Am 2 O 3 systems and on correlations obtained of the measured melting with O/M ratio and with burnup, an equation was derived expressing the estimated melting temperature T rev (K) as function of the factors mentioned above that affect the temperature:, where X 1 is the plutonium fraction (Pu/(Pu+U)), X 2 the americium fraction (Am/(Pu+U+Am)), X 3 the burnup (GWd/t), and X 4 the O/M ratio (−) (not exceeding 2.00). Toward advanced stage of burnup, the tendency of irradiated fuel melting temperature to lower with burnup progress presented a tendency to level off its rate of descent.

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“…However we have to quote that the slope is obtained for largely scattered data ($±20 K). For pressures lower than 0.05 Gpa the [49] 3138 ± 30 Kjaerheim and Rolstad (1969) [38] 3138 ± 20 Latta and Fryxell (1970) [9] 3138 ± 15 Tachibana et al (1985) [41] 3118 ± 25 Matzke et al (1993) [45] 3140 ± 15…”

Section: Liquidus and Solidus In The Uo 2±x Rangementioning

confidence: 99%