An advanced model for grain face diffusion transport in irradiated UO2 fuel. Part 1: Model formulation

Veshchunov, M.S.; Тарасов, В. И.

doi:10.1016/j.jnucmat.2009.03.055

Cited by 15 publications

(3 citation statements)

References 21 publications

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“…These codes are coupled to nuclear databases, such as JEFF-3 (The Joint Evaluated Fission and Fusion File, OECD-NEA) [8] or ENDF (Evaluated Nuclear Data File, USA) [9], which contain fission cross sections and fission yield values. Fuel performance codes, such as ALCYONE [10], MFPR [11], or BISON [12], usually contain a simplified module (PRODHEL for ALCYONE [13], BONUS for MFPR [14]) for fission rate density calculations, validated against more accurate neutron transport codes [15]. The coupling of fuel performance and neutronics codes is still an area of active research [16,17].…”

mentioning

confidence: 99%

Unit mechanisms of fission gas release: Current understanding and future needs

Tonks

Andersson

Devanathan

et al. 2018

Journal of Nuclear Materials

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Gaseous fission product transport and release has a large impact on fuel performance, degrading fuel and gap properties. While gaseous fission product behavior has been investigated with bulk reactor experiments and simplified analytical models, recent improvements in experimental and modeling approaches at the atomistic and mesoscales are beginning to reveal new understanding of the unit mechanisms that define fission product behavior. Here, existing research on the basic mechanisms of fission gas release during normal reactor operation are summarized and critical areas where work is needed are identified. This basic understanding of the fission gas behavior mechanisms has the potential to revolutionize our ability to predict fission product behavior and to design fuels with improved performance. In addition, this work can serve as a model on how a coupled experimental and modeling approach can be applied to understand the unit mechanisms behind other critical behaviors in reactor materials.

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mentioning

confidence: 99%

Unit mechanisms of fission gas release: Current understanding and future needs

Tonks

Andersson

Devanathan

et al. 2018

Journal of Nuclear Materials

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“…As explained in reference [21], the original Nelson model is used for intergranular porosity without modifications, suggested in reference [22] for intragranular bubbles (in order to avoid duplication of the backward flux of atoms, struck from pores, to the grain boundary).…”

Section: Fission Gas Capture By Poresmentioning

confidence: 99%

Modelling of as-fabricated porosity in UO₂fuel by MFPR code

Тарасов

Veshchunov

2016

EPJ Nuclear Sci. Technol.

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Abstract. For consistent modelling of behaviour of as-fabricated porosity in UO 2 fuel irradiated under various conditions of in-pile and out-of-pile tests as well as under normal and abnormal conditions of nuclear reactor operation, the additional analysis of experimental observations and critical assessment of available models are presented. On this base, the mechanistic MFPR code, including physically-grounded models for the fuel porosity evolution in UO 2 fuel under various irradiation and thermal regimes, is refined. These modifications complete the consistent description of the fuel porosity evolution in the MFPR code and result in a notable improvement of the code predictions.

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“…An unirradiated UO 2 fuel has as-fabricated pores introduced by sintering process [3,4] and an irradiated UO 2 fuel has bubbles formed by coalescence of gaseous fission products [1,5]. The porosity in UO 2 makes the thermal conductivity of porous UO 2 lower than that of dense UO 2 because thermal conductivity of a bubble is much lower [1].…”

Section: Introductionmentioning

confidence: 99%