A model for the influence of microstructure, precipitate pinning and fission gas behavior on irradiation-induced recrystallization of nuclear fuels

Rest, J.

doi:10.1016/j.jnucmat.2004.01.009

Cited by 46 publications

(28 citation statements)

References 25 publications

(47 reference statements)

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“…Several recent models were developed or are still in development such as the V.Likhanskii [32] model based on the mathematical model proposed by M.Kinoshita [33], the J.Rest [34,35] model or the model developed in START3 by G.Khvostov [36]. These improved models consider that the HBS transformation is initiated on grain boundaries and that gas precipitation and grain subdivision propagation are simultaneous phenomena.…”

Section: Mechanism For the Hbs Transformationmentioning

confidence: 99%

Discussion About HBS Transformation in High Burn-Up Fuels

Baron¹,

Kinoshita²,

Thévenin³

et al. 2009

Nuclear Engineering and Technology

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Section: Mechanism For the Hbs Transformationmentioning

confidence: 99%

Discussion About HBS Transformation in High Burn-Up Fuels

Baron¹,

Kinoshita²,

Thévenin³

et al. 2009

Nuclear Engineering and Technology

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“…The fission density F d dependent concentration of viable recrystallization nuclei C rx was determined as a function of the dislocation density q d based on the concept of node pinning by irradiation-induced precipitates associated with fission-gas bubbles [1] as…”

Section: Review Of Model For Initiation Of Irradiation-induced Recrysmentioning

confidence: 99%

“…As such, F dx is independent of e v and e i and depends primarily on the collision related parameters k, D g and a p //c. Substituting nominal values of the parameters [1] in Eq. (4) leads to the simplified expression 1 for F dx (m À3 ):…”

Section: Is a Constant Of Proportionality And _mentioning

confidence: 99%

“…Irradiation-induced recrystallization appears to be a general phenomenon in that it has been observed to occur in a variety of nuclear fuel types [1], e.g. U-xMo, UO 2 , and U 3 O 8 .…”

Section: Introductionmentioning

confidence: 99%

“…The recrystallization process results in sub-micron size grains that accelerate fissiongas swelling due to the combination of short diffusion distances, increased grain-boundary area per unit volume, and greater intergranular bubble growth rates as compared to that in the grain interior [2]. Previously, an expression has been derived for the fission density at which irradiation-induced recrystallization is initiated that is athermal and weakly dependent on fission rate [1]. The initiation of recrystallization is to be distinguished from the subsequent progression and eventual consumption of the original fuel grain.…”

Section: Introductionmentioning

confidence: 99%

See 2 more Smart Citations

A model for the effect of the progression of irradiation-induced recrystallization from initiation to completion on swelling of UO2 and U–10Mo nuclear fuels

Rest

2005

Journal of Nuclear Materials

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Fission Gas and Bias‐Driven Swelling of Nuclear Fuels

Rest

2015

Materials Science and Technology

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The article contains sections titled: Introduction Behavior of Gaseous Fission Products for Normal Reactor Conditions Gaseous Fission Product Behavior Nucleation and Growth of Intragranular Fission Gas Bubbles Intergranular Fission Gas: Grain Faces and Edges Bubble Interlinkage Intra‐ and Intergranular Bubble Swelling Fuel Element Swelling Solid Fission Product Swelling Fission Gas Swelling at Low Temperature/Low Burnup Fission Gas Swelling at Low Temperature/High Burnup Fission Gas Swelling at High Temperature Fission Gas Release Grain Size Effects on Gas Release Validation of FASTGRASS Model for Fission‐Gas Release DART : Dispersion Analysis Research Tool Mechanical Model Mechanical Model with Aluminide Formation DART Calculational Algorithms DART Validation Cavitational Swelling of α‐Uranium Zone in U–Pu–Zr Fuel Comparison with Data from U–10Zr and U–19Pu–10Zr Fuel Elements Behavior of Fission Products under Reactor Transient Conditions Prediction of Fuel Ductility under Transient Heating Microcracking Grain Growth/Grain‐Boundary Sweeping Mobility of Fission Gas Bubbles under Transient Conditions Fission Gas Release during Transient Conditions Modeling the Behavior of Volatile Fission Products ( VFPs ) VFP Chemistry VFP Release under Normal Operating Conditions VFP Release during Transient Heating Effect of Fuel Heating Rate on VFP Release Effect of Fuel Burnup on VFP Release Effect of Fuel Irradiation Temperature on VFP Release Effect of Cesium Chemistry on VFP Release Fission Gas Behavior in Amorphous Nuclear Fuels Model of Amorphous Fuel Bubble Growth at the Knee Bubble Growth after the Knee‐Point Comparison with Data Example of a Calculated Fuel Property Introduction Viscosity Model for Binary Alloys Undergoing Amorphization Looking Forward

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A model for the influence of microstructure, precipitate pinning and fission gas behavior on irradiation-induced recrystallization of nuclear fuels

Cited by 46 publications

References 25 publications

Discussion About HBS Transformation in High Burn-Up Fuels

Discussion About HBS Transformation in High Burn-Up Fuels

A model for the effect of the progression of irradiation-induced recrystallization from initiation to completion on swelling of UO2 and U–10Mo nuclear fuels

Fission Gas and Bias‐Driven Swelling of Nuclear Fuels

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