Thermophysical properties of uranium dioxide

Fink, J.K.; Chasanov, M.G.; Leibowitz, L.

doi:10.1016/0022-3115(81)90541-9

Cited by 117 publications

(71 citation statements)

References 21 publications

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“…2 shows the models proposed by Ronchi [1], Fink [2], and Dias [8], respectively Eqs. (1), (2) and (7).…”

Section: Resultsmentioning

confidence: 99%

“…The results will be compared with the results obtained using the models proposed by Ronchi et al [1] and Fink et al [2] that had been presented in Section 2.…”

Section: Specifications Of the Nuclear Fuel Rod Simulatedmentioning

confidence: 96%

“…From a set of experimental information fuller than that used by Ronchi et al [1], Fink recommended the use of the following expression for the thermal conductivity of UO 2 samples with a 95% theoretical density [2]:…”

Section: Model Proposed By Fink Et Almentioning

confidence: 99%

“…With the evolution of the technology, theoretical and experimental researchers have been trying to streamline the empirical equations that predict the thermal conductivity of UO 2 , incorporating new models for the phonons and including the dependency of temperature in its functional form [1,2]. Due to the low thermal conductivity of the fuel material (UO 2 ), a quite steep temperature gradient appears in the pellet.…”

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confidence: 99%

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Evaluation of Nuclear Fuel Centerline Temperature Using New UO2 Thermal Conductivity Models

Palma¹,

Mesquita²,

Marinho³

et al. 2014

JEPE

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Abstract:The nuclear industry needs of prediction of behavior and life-time, for a wide range of normal, off-normal and accident conditions for safe and economic operation. Among different thermo-mechanical properties that can be predictable, the knowledge on the radial temperature distribution of the UO 2 (uranium dioxide) nuclear fuel during the operation of nuclear reactors is essential for safety as different mechanical and thermal-hydraulic thresholds should be respected. One of the attributes of the Brazilian CNEN (Nuclear Energy Commission) is to assess the performance of the fuel rods used in these reactors in high-burnup regimes. The effective removal of the heat generated in the fuel rods constitutes one of the primary points to consider in the design of nuclear reactors. One of the important physical parameters in the study of heat conduction from the nuclear fuel to the coolant in a PWR (pressurized water reactor) is its thermal conductivity. It is therefore desirable that the empirical models, updated for the calculation of thermal conductivity in the fuel region be developed from new sets of experimental data from the irradiated fuel rods in controlled environments. This paper presents the obtained results of implementing of a new model for thermal conductivity of the UO 2 in the FRAPCON code.

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“…2 shows the models proposed by Ronchi [1], Fink [2], and Dias [8], respectively Eqs. (1), (2) and (7).…”

Section: Resultsmentioning

confidence: 99%

“…The results will be compared with the results obtained using the models proposed by Ronchi et al [1] and Fink et al [2] that had been presented in Section 2.…”

Section: Specifications Of the Nuclear Fuel Rod Simulatedmentioning

confidence: 96%

Section: Model Proposed By Fink Et Almentioning

confidence: 99%

mentioning

confidence: 99%

See 2 more Smart Citations

Evaluation of Nuclear Fuel Centerline Temperature Using New UO2 Thermal Conductivity Models

Palma¹,

Mesquita²,

Marinho³

et al. 2014

JEPE

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“…From these heat capacity data, the enthalpy, entropy, and Gibbs energy functions were computed. These results are presented in Tables 5-7 [18].…”

Section: Calorimetric Measurementsmentioning

confidence: 92%

Thermophysical properties of uranium–europium mixed oxides

et al. 2015

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Uranium-europium mixed oxides (U 1y Eu y )O 2x (y = 0.2-0.8) were prepared by the citrate gel combustion technique and characterized by X-ray diffraction (XRD). Single phase fluorite structure was observed in those solid solutions with y ≤ 0.6. The solid solutions with y > 0.6 were found to be biphasic, with the second phase being cubic Eu 2 O 3 . Heat capacity and enthalpy increment measurements were carried out by using differential scanning calorimeter (DSC) and drop calorimeter in the temperature range 298-800 K and 800-1800 K, respectively. The , p m C values at 298 K for (U 1y Eu y )O 2x (y = 0.2, 0.4, 0.6) are 64.8, 64.6, and 63.5 J·K 1 ·mol 1 , respectively. An anomalous increase was observed in the heat capacity in all of the solid solutions with the onset temperature around 950 K. This could be attributed to the contribution from Frenkel pair oxygen defects. From the excess heat capacity data, the enthalpy for the formation of these defects was computed and found to be in the range of 2.10±0.02 eV.

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Oxide Fuels

Lambert

Strain

2006

Materials Science and Technology

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Thermophysical properties of uranium dioxide

Cited by 117 publications

References 21 publications

Evaluation of Nuclear Fuel Centerline Temperature Using New UO2 Thermal Conductivity Models

Evaluation of Nuclear Fuel Centerline Temperature Using New UO2 Thermal Conductivity Models

Thermophysical properties of uranium–europium mixed oxides

Oxide Fuels

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