A new fission-gas release model

White, Ronald J.; Tucker, M.O.

doi:10.1016/0022-3115(83)90176-9

Cited by 231 publications

(107 citation statements)

References 31 publications

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“…Speight (1 969) produced one of the early studies on the complexity of resolution at the grainboundary surface, and Turnbull (1974), White and Tucker (1983), Rest (1980), and Forsberg and Massih (1 985) carried this work forward. Lanning and Bradley (1984), Manzel(1993), and Barner et al (1 990) and others have reported attempts to quantify the partition of the produced gas between grain-boundary and matrix fractions in specific fuel samples.…”

Section: Experimental Evidence For Grain-boundary Gas Storage and Relmentioning

confidence: 99%

“…Thus, a model that recognizes bubble formation on grain boundaries can release the observed "additional FGR" that diffisice alone will not release in the short time of power ramps. Multi-stage gas release models have been proposed by Electric Power Research Institute (EPRI) (Fiero et al 1987), Argonne National Laboratory (Rest 1980), and the British Central Electricity Generating Board (CEGB) (White and Tucker 1983) among others. The EPRI model was extensively tested at Pacific Northwest National Laboratory against high-burnmp cases from pressurized water reactors (PWRs), boiling water reactors (BWRs) and test reactors.…”

Section: Introductionmentioning

confidence: 99%

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FRAPCON-3: Modifications to fuel rod material properties and performance models for high-burnup application

Lanning¹,

Beyer²,

Painter³

1997

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Section: Experimental Evidence For Grain-boundary Gas Storage and Relmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

FRAPCON-3: Modifications to fuel rod material properties and performance models for high-burnup application

Lanning¹,

Beyer²,

Painter³

1997

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“…In the current analysis, the pores are considered as intergranular lenticular voids with the dihedral angle u = 50°. Their volume, V, and surface area, S, are [7]:…”

Section: Initial Fuel Porositymentioning

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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“…On the other hand, the released gas brings about a pressure rise and thermal conductivity degradation of the rod filling gas. Both fission gas swelling and release therefore affect the thermo-mechanical performance of the fuel rod and may eventually lead to cladding failure, especially at high burn-up and during power transients [5]. Hence, the description of fission gas behaviour is an essential aspect of fuel rod analysis.…”

Section: Introductionmentioning

confidence: 99%

“…It is therefore essential to have a model that is simple enough to compute the fractional release from and gaseous swelling in the grains in an efficient manner to an accuracy that is better than or equivalent to the experimental scatter. The degree of simplicity of the model in a fuel performance code is largely justified by the uncertainties pertaining to some of the parameters like diffusion coefficients (at least a factor of 10) [5][6][7].…”

Section: Introductionmentioning

confidence: 99%