On the thermal conductivity of UO2 nuclear fuel at a high burn-up of around 100MWd/kgHM

Walker, C.T.; Staicu, D.; Sheindlin, M.; Papaioannou, D.; Goll, W.; Sontheimer, F.

doi:10.1016/j.jnucmat.2005.11.007

Cited by 71 publications

(38 citation statements)

References 21 publications

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“…The radial burn-up distribution in a UO 2 nuclear fuel pellet with an average burn-up of about 100 MWd/kgHM (reprinted from ref. [22] with permission of Elsevier). The local burn-up increases sharply at the fuel surface due to the fission of plutonium created from uranium by neutron capture.…”

Section: Determination Of the Local Burn-up In Irradiated Nuclear Fuelmentioning

confidence: 99%

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Microbeam analysis of irradiated nuclear fuel

Walker¹,

Stephan²,

Pöml³

et al. 2012

IOP Conf. Ser.: Mater. Sci. Eng.

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Abstract. Microbeam analysis is widely used in the nuclear power industry. It is used to characterise the as-fabricated fuel, for routine post-irradiated examination and for research into the mechanisms of phenomena that limit the energy production of the fuel. The techniques most commonly used are wavelength-dispersive electron probe microanalysis, scanning electron microscopy and secondary ion mass spectrometry. Other microbeam analysis techniques that have been successfully applied to irradiated nuclear fuel are transmission and replica electron microscopy, X-ray fluorescence and micro X.-ray diffraction. Specific examples illustrating the past and present use of microbeam analysis in nuclear research establishments are presented with emphasis on the unique results they provide. As an aid to understanding, some basic facts about nuclear fuel rods and their irradiation are first given. This is followed by a description of features that set apart the microbeam analysis of high radioactive materials from standard practice.

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Section: Determination Of the Local Burn-up In Irradiated Nuclear Fuelmentioning

confidence: 99%

“…The high burn-up structure in the outer region of a UO 2 fuel pellet as revealed by scanning electron microscopy (reprinted from ref. [22] with permission from Elsevier).…”

Section: Re-crystallisation Of Nuclear Fuel At High Burn-upmentioning

confidence: 99%

Microbeam analysis of irradiated nuclear fuel

Walker¹,

Stephan²,

Pöml³

et al. 2012

IOP Conf. Ser.: Mater. Sci. Eng.

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“…Recently, the tendency of increasing fuel burn-up (BU) produces 239 Pu by neutron capture of 238 U generating an external layer with a higher local BU, which presents higher porosity and fuel grain subdivision, resulting on the formation of the so-called rim zone also known as high burn-up structure (HBS) [9,10]. This layer is observed for BU's higher than 40 MWd·kgU -1 [9][10][11][12][13][14][15][16] and is a function of BU and the irradiation temperature, being the temperature threshold 1100ºC [13,15]. As a conservative approach for those SNF's, the radionuclides located in the HBS were also included in the IRF [6,8].…”

Section: Introductionmentioning

confidence: 99%

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

González-Robles

Serrano‐Purroy

Sureda

et al. 2015

Journal of Nuclear Materials

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The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercises to govern the dose that could arise from the repository. A conservative definition of IRF comprises the total inventory of radionuclides located in the gap, fractures, and the grain boundaries and, if present, in the high burn-up structure (HBS). The values calculated from this theoretical approach correspond to an upper limit that likely does not correspond to what it will be expected to be instantaneously released in the real system. Trying to ascertain this IRF from an experimental point of view, static leaching experiments have been carried out with two commercial UO2 spent nuclear fuels (SNF): one from a pressurized water reactor (PWR), labelled PWR, with an average burn-up (BU) of 52 MWd·kgU

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“…When comparing the predictions of TUBRNP with radiochemical and EPMA data for UO 2 fuel irradiated in a commercial PWR up to a burn-up of 102 MWd/kgHM [17,18], the average Pu content in the fuel section analysed was under-predicted by 20%. In line with the models included in the RTOP code and COSMOS code, it was considered coping with this deviation by introducing the burn-up (or time) dependence in the model parameters.…”

Section: Extension Of the Tubrnp Modelmentioning

confidence: 99%