Analysis of fission product ingots formed in uranium-plutonium oxide irradiated in EBR-II

O'Boyle, D.R.; Brown, F.L.; Dwtght, A.E

doi:10.1016/0022-3115(70)90210-2

Cited by 35 publications

(6 citation statements)

References 8 publications

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“…Many authors have reported the particle size and chemical composition of this phase [9][10][11][12][13][14][15]. The reported composition is variable, but tends to be largely Mo and Ru with smaller amounts of Tc, Rh, and Pd.…”

Section: Introductionmentioning

confidence: 94%

Dissolution of spent nuclear fuel in carbonate–peroxide solution

Soderquist

Hanson

2010

Journal of Nuclear Materials

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Section: Introductionmentioning

confidence: 94%

Dissolution of spent nuclear fuel in carbonate–peroxide solution

Soderquist

Hanson

2010

Journal of Nuclear Materials

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“…The most abundant secondary phases observed in fuel are the noble metal or "white phases." They are inclusions in fuel and are readily seen in micrographs of irradiated fuel samples [38][39][40]. Kaye et al [41] have performed an assessment for the 5 noble metal alloy (Mo-Pd-Rh-Ru-Tc) that can form in fuel under irradiation and developed useful regular solution models for the potential fcc, hcp, and bcc phases.…”

Section: Metallic Phasesmentioning

confidence: 99%

Application of thermochemical modeling to assessment/evaluation of nuclear fuel behavior

Besmann

McMurray

Simunovic

2016

Calphad

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The combination of new fuel compositions and higher burn-ups envisioned for the future means that representing fuel properties will be much more important, and yet more complex. Behavior within the oxide fuel rods will be difficult to model owing to the high temperatures, and the large number of elements generated and their significant concentrations that are a result of fuels taken to high burn-up. This unprecedented complexity offers an enormous challenge to the thermochemical understanding of these systems and opportunities to advance solid solution models to describe these materials. This paper attempts to model and simulate that behavior using an oxide fuels thermochemical description to compute the equilibrium phase state and oxygen potential of LWR fuel under irradiation.

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“…It is known that some FPs are soluble in the fuel matrix and others form metallic or oxide inclusions. [1][2][3][4][5][6] As the inclusions, the white metallic precipitates composed of Mo-Tc-Ru-Rh-Pd alloys and oxide precipitates with a perovskite-type structure of (Ba,Sr) (U,Pu,Zr,RE,Mo)O 3 have been observed. It is considered that the inclusions affect the thermochemical and thermophysical properties of the fuel, especially the thermal conductivity, which is the most essential property.…”

Section: Introductionmentioning

confidence: 99%

“…In high burn up UO 2 nuclear fuel, a number of FPs is produced. It is known that some FPs are soluble in the fuel matrix and others form metallic or oxide inclusions 1–6 . As the inclusions, the white metallic precipitates composed of Mo–Tc–Ru–Rh–Pd alloys and oxide precipitates with a perovskite‐type structure of (Ba,Sr) (U,Pu,Zr,RE,Mo)O 3 have been observed.…”

Section: Introductionmentioning

confidence: 99%

Thermophysical Properties of Perovskite‐Type Strontium Cerate and Zirconate

Yamanaka

Kurosaki

Oyama

et al. 2005

Journal of the American Ceramic Society

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Polycrystalline samples of strontium series perovskite‐type oxides, SrCeO3 and SrZrO3, were prepared and the thermophysical properties were measured. The chemical compositions of the samples do not deviate from the stoichiometric composition. The oxygen‐to‐metal (O/M) ratios of SrCeO3 and SrZrO3 are 3.00±0.03 and 2.98±0.01, respectively. The average linear thermal expansion coefficients are 1.11 × 10−5 K−1 for SrCeO3 and 9.69 × 10−6 K−1 for SrZrO3 in the temperature range between 300 and 1000 K. The melting temperatures Tm of SrCeO3 and SrZrO3 are 2266 and 2883 K, respectively. The longitudinal and shear sound velocities were measured by an ultrasonic pulse–echo method at room temperature in air, which enables to evaluate the elastic moduli and Debye temperature. The heat capacity was measured by using a differential scanning calorimeter in high‐purity argon atmosphere. The thermal diffusivity was measured by a laser flash method in vacuum. The thermal conductivities of SrCeO3 and SrZrO3 at room temperature are 2.95 and 4.06 W·m−1·K−1, respectively.

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Analysis of fission product ingots formed in uranium-plutonium oxide irradiated in EBR-II

Cited by 35 publications

References 8 publications

Dissolution of spent nuclear fuel in carbonate–peroxide solution

Dissolution of spent nuclear fuel in carbonate–peroxide solution

Application of thermochemical modeling to assessment/evaluation of nuclear fuel behavior

Thermophysical Properties of Perovskite‐Type Strontium Cerate and Zirconate

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