Lattice parameters of (U, Pu, Am, Np)O2−x

Kato, Masato; Konashi, Kenji

doi:10.1016/j.jnucmat.2008.09.037

Cited by 53 publications

(43 citation statements)

References 12 publications

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“…Physical property measurements, fuel pellet preparation tests, and irradiation tests of Np-and Am-bearing MOX (Np/Am-MOX) fuels have been carried out as a part of the development. [4][5][6][7][8][9][10][11][12][13][14][15][16][17] To develop such new fuels, it is essential to evaluate irradiation behavior. However, irradiation data is little in the early phase of development.…”

Section: Introductionmentioning

confidence: 99%

“…[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%

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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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Section: Introductionmentioning

confidence: 99%

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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“…Pu content is known to increase the oxygen potential. Several groups have investigated the effect of Am and Np addition in (U,Pu)O 2 (Kato et al, 2009;Nakamichi et al, 2011). They found that the addition of Am caused the oxygen potential to increase, but Np addition did not affect the oxygen potential.…”

Section: Discussionmentioning

confidence: 99%

“…Uranium and plutonium mixed oxide (U,Pu)O 2 , which is used in nuclear fuels, is a substitutional solid solution compound having the CaF 2 type fluorite structure as shown in Fig.1 (Markin & Street, 1967;Sari et al, 1970;Kato & Konashi, 2009). (U,Pu)O 2 is stable in a wide range region of hyper-and hypo-stoichiometric compositions.…”

Section: Introductionmentioning

confidence: 99%

Oxygen Potentials and Defect Chemistry in Nonstoichiometric (U,Pu)O2

Kato¹

2012

Stoichiometry and Materials Science - When Numbers Matter

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“…Stoichiometry significantly affects physical properties such as lattice parameters, oxygen potentials and melting temperatures [1][2][3][4]. Therefore, it is important to understand the characterictics of the defects in the non-stoichiometric composition for evaluation of the physical property change of PuO 2-x .…”

Section: Introductionmentioning

confidence: 99%

Measurement of oxygen chemical diffusion in PuO_2‐x and analysis of oxygen diffusion in PuO_2‐x and (Pu,U)O_2‐x

Kato

Uchida

Sunaoshi³

2012

Phys. Status Solidi C

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All available oxygen potential-temperature-composition data for the calcium fluorite-structure ** phase were retrieved from the literature and utilized in the development of a binary solid solution representation of the phase. The data and phase relations are found to be best described by a solution of [Pui^C^] and [PuO 2 ] with a temperature dependent interaction energy. The fluorite-structure is assumed to be represented by a combination of the binaries' and CUO^^, and thus treated as a solution of [Pu^/302], [PuO 2 ], [UO 2 ], and either [U 2 0i,.5] or [U3O7]. The resulting equations well reproduce the large amount of oxygen potential-temperature-composition data for the mixed oxide system, all of which were also retrieved from the literature. These models are the first that appear to display the appropriate oxygen potential-temperature-composition and phase relation behavior over the entire range of existence for the phases.

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Lattice parameters of (U, Pu, Am, Np)O2−x

Cited by 53 publications

References 12 publications

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

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

Oxygen Potentials and Defect Chemistry in Nonstoichiometric (U,Pu)O2

Measurement of oxygen chemical diffusion in PuO_2‐x and analysis of oxygen diffusion in PuO_2‐x and (Pu,U)O_2‐x

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Lattice parameters of (U, Pu, Am, Np)O2−x

Cited by 53 publications

References 12 publications

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

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

Oxygen Potentials and Defect Chemistry in Nonstoichiometric (U,Pu)O2

Measurement of oxygen chemical diffusion in PuO2‐x and analysis of oxygen diffusion in PuO2‐x and (Pu,U)O2‐x

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Measurement of oxygen chemical diffusion in PuO_2‐x and analysis of oxygen diffusion in PuO_2‐x and (Pu,U)O_2‐x