1985
DOI: 10.1016/0022-3115(85)90323-x
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Experimental and thermodynamic evaluation of the melting behavior of irradiated oxide fuels

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Cited by 77 publications
(50 citation statements)
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“…11) This dependence is revealed also in Fig. 3, where a larger lowering of solidus temperature is seen between Pu fractions of 0.17 to 0.18 than that of 0.29.…”
Section: Influence Of Burnup On Melting Temperature: T Solfpsupporting
confidence: 57%
“…11) This dependence is revealed also in Fig. 3, where a larger lowering of solidus temperature is seen between Pu fractions of 0.17 to 0.18 than that of 0.29.…”
Section: Influence Of Burnup On Melting Temperature: T Solfpsupporting
confidence: 57%
“…ThO2 3650-3675 3663 ± 100 Benz et al [6] 3643 ± 30 Rand et al [7] 3573 ± 100 Lambertson et al [8] 3651 ± 17 Ronchi et al [9] 3624 ± 108 Bohler et al [10] UO2 3050-3075 3113 ± 20 Lyon et al [11] 3138 ± 15 Latta et al [12] 3075 ± 30 Ronchi et al [13] 3120 ± 30 Adamson et al [14] 3,113.15 MATPRO [15] 3138 ± 15 Komatsu et al [16] 3120 ± 30 ORNL [17] 3050 ± 55 Böhler et al [18] PuO2 2800-2825 2663 ± 20 Lyon et al [11] 2701 ± 35 Adamson et al [14] 2647 MATPRO [15] 2718 Komatsu et al [16] 2701 ± 35 ORNL [17] 2843 Kato et al [19] Table 4: MD calculated enthalpy increments (in J/mole) of solid and liquid phases of (Th,U)O2 and (Th,Pu)O2 MOX are fitted to equation (7) and (8), respectively and coefficients are enlisted.…”
Section: Calculated Temperature Range (K) Experimental Values (K)mentioning
confidence: 99%
“…Experimentally reported melting temperatures of UO2 vary from 3050 K to 3138 K ( Table 2) [11][12][13][14][15][16][17][18]. The melting point of UO2 given in MATPRO [15] is 3113.15 K, based on the equations for the solids and liquids boundaries of the UO2-PuO2 phase diagram given by Lyon et al [11].…”
Section: Enthalpy and Density Variation Of Th Rich (Thu)o2 And (Thpmentioning
confidence: 99%
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“…[8][9][10][11][12][13][14][15] Derivation of the equation proceeded in three steps, making reference to published reports where available: (1) Derive the liquidus temperature equation for unirradiated stoichiometric MOX fuel [8][9][10] and evaluate liquidus temperature lowering brought by the presence of Am and by the alteration herewith of fuel stoichiometry (oxygen-to-metal ratio (O/M) ratio), applying the procedure adopted previously for deriving the solidus temperature equation. Thereafter, the change with progress of burnup brought to the interval between the solidus and liquidus temperatures is calculated using the solidus and liquidus equations.…”
mentioning
confidence: 99%