The thermal conductivity of ovides of uranium, neptunium and americium at elevated temperatures

Schmidt, H.E.; Sari, C.; Richter, K.; Gerontopoulos, P.

doi:10.1016/0022-5088(86)90578-3

Cited by 21 publications

(14 citation statements)

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“…Only the fabrication technology and oxygen potential for (U,Pu,MA)O 2 have been reported by Yoshimochi et al 3) and Osaka et al, 4) respectively. Although the thermal conductivity of (U,MA)O 2 has been reported by Schmidt et al,5) the thermal properties such as the thermal expansion coefficient, heat capacity and thermal conductivity of (U,Pu,MA)O 2 have not been reported until now. Therefore, it is necessary to develop a new technique to evaluate the physical properties of MA-containing materials.…”

Section: Introductionmentioning

confidence: 94%

Molecular Dynamics Studies of Americium-Containing Mixed Oxide Fuels

Kurosaki

Adachi

Katayama

et al. 2006

Journal of Nuclear Science and Technology

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The molecular dynamics (MD) calculation was performed for americium-containing mixed oxide fuels, (U 0:7Àx Pu 0:3 Am x )O 2 (x¼0; 0:016; 0:03; 0:05; 0:1; 0:15), in the temperature range from 300 to around 2,500 K to evaluate the lattice parameter, heat capacity and thermal conductivity. The MD results reveal that the calculated heat capacity and thermal conductivity are at a similar level in the entire composition range, in other words they are scarcely influenced by adding americium up to 15%. This behavior was examined from a view point of a phonon-impurity scattering mechanism.

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Section: Introductionmentioning

confidence: 94%

Molecular Dynamics Studies of Americium-Containing Mixed Oxide Fuels

Kurosaki

Adachi

Katayama

et al. 2006

Journal of Nuclear Science and Technology

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“…Early studies on the physical properties of MAbearing oxide showed that Am addition significantly affected melting temperatures, thermal conductivities and oxygen potentials. [18][19][20] However, the physical properties of MOX containing 0-3% Am and 0-12% Np have been measured in recent studies, and it was found that the effect of Np and Am addition on the properties was small. [7][8][9][10][11][12][13][14][15][16][17] In this work, the physical properties of Np/Am-MOX were evaluated, and the irradiation behavior was analyzed by using those properties, which contribute to the development of the model for describing irradiation behavior.…”

Section: Introductionmentioning

confidence: 99%

Physical Properties and Irradiation Behavior Analysis of Np- and Am-Bearing MOX Fuels

Kato

Maeda

Ozawa

et al. 2011

Journal of Nuclear Science and Technology

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The physical properties and irradiation behavior of Np-and Am-bearing MOX were evaluated for the development of advanced fast reactor fuels. The physical properties, lattice parameter, melting temperature, thermal conductivity, and oxygen potential of the fuels were described as functions of Np content, Am content, and oxygen-to-metal (O=M) ratio, and the effect of a few percent Np and Am addition into MOX on those properties was found to be negligibly small. The irradiation tests of fuel pellets having O=M ratios of 1.98 or 1.96 were carried out at a high linear heat rate of about 430 W/cm for 24 h. The redistributions of actinide element and oxygen were analyzed by using the physical properties for Np-and Am-bearing MOX, and the maximum temperatures of the pellets were estimated. The maximum temperatures of the pellets of O=M ¼ 1:96 and 1.98 were estimated to be 2,701 and 2,510 K, respectively. The analysis result showed that the higher maximum temperature in the low-O=M pellet was caused by the low thermal conductivity in the outer region of the pellets, and the maximum temperatures of the pellets did not exceed their melting temperatures. In the results of postirradiation examination, no trace of melting was observed.

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“…It is reported that the oxygen potentials of Am-containing UO 2 -based fuels with a fluorite structure are high [5,6], while those of Np-containing UO 2 -based fuel are at the same level as those of MOX [7]. Although the oxygen potential of Am-containing UO 2 -based fuels can be reduced by a lowering of the O/M ratio, it could cause other significant problems, especially in terms of thermal performances of the fuel [8,9]. Alternative Am-containing fuels should, therefore, be developed.…”

Section: Introductionmentioning

confidence: 97%