A new code for predicting the thermo-mechanical and irradiation behavior of metallic fuels in sodium fast reactors

Karahan, Aydın; Buongiorno, Jacopo

doi:10.1016/j.jnucmat.2009.11.022

Cited by 56 publications

(59 citation statements)

References 32 publications

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“…Substituting , according to Karahan,9 , from Churchman 10 for pure U, obtain fuel swelling due to fission gas: ,…”

Section: Fuel Swelling Due To Fission Gas and Fission Gas Releasementioning

confidence: 99%

Fuel performance modeling results for representati

Medvedev¹

2012

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Approved by: INTENTIONALLY BLANK vii SUMMARYThe objective of the present study was to predict the outcome of the AFC-3A annular U-10Zr fuel irradiation experiment. Specifically, the study attempted to predict whether the annular fuel will swell inward and fill the annulus, or swell outward resulting in an undesirable cladding deformation.It was predicted that both 55% and 75% annular fuels operating at 350 W/cm for 201 days will swell inward and partially fill the annulus which signifies a positive outcome of the experiment. The driving mechanism for such behavior is the fuel creep under the compressive stress exerted on the fuel by the cladding as a result of the fuel cladding mechanical interaction.Comparison with the solid fuel revealed that the annular fuel is expected to swell less early in life due to the mechanical constraint provided by the cladding. Furthermore, mechanical constraint is expected to yield a marked reduction of the axial elongation of the annular fuel as compared to the solid fuel. The prediction is based on the assumption that the annular fuel is not capable of moving axially relative to the cladding after the two come in contact. Post irradiation examination results would be very useful to assess the validity of this assumption. Specifically, underprediction of the axial growth would point to the fact that some slippage of the fuel relative to the cladding occurs after the onset of the FCMI.As fuel creep plays the major role in the deformation of the annular fuel, the contributions from the thermal and irradiation induced creep to the total creep rate of fuel were examined to provide guidance for possible creep testing experiments of the fuel (separate effect tests). It was found that irradiation induced creep dominates deformation of the fresh fuel at low temperatures. At high temperatures, and in the case of porous fuel, the thermal creep of the fuel becomes dominant and irradiation induced creep can be neglected. Fission gas induced porosity seems to accelerate fuel creep drastically. Recognizing the sensitivity of the fuel creep to the porosity, additional studies exploring this phenomenon and verifying published equations either experimentally or through computation may benefit the understanding of the annular fuel behavior. viii INTENTIONALLY BLANK ix CONTENTS

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“…Substituting , according to Karahan,9 , from Churchman 10 for pure U, obtain fuel swelling due to fission gas: ,…”

Section: Fuel Swelling Due To Fission Gas and Fission Gas Releasementioning

confidence: 99%

Fuel performance modeling results for representati

Medvedev¹

2012

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“…The only different treatment in this work is the omission of a volumetric factor in the expression of intergranular gas density for the recrystallized grain area. As for mechanical influence, evidence indicated that the hydrostatic pressure could affect the gas bubble swelling [11][12][13][14][15]. Ideally, UMo fuel meat is considered sealed by Al alloy cladding, allowing no fission gas release to free volume under normal operation.…”

Section: Introductionmentioning

confidence: 99%

Modifications and applications of the mechanistic gaseous swelling model for UMo fuel

Cui

Ding

Chen

et al. 2015

Journal of Nuclear Materials

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“…At the beginning of irradiation, most of the fuel is in the a + d-phase field with only the hottest part of the fuel in the high temperature c 1 + c 2 or c field [14,15]. For a typical fuel pin, the metal fuel slug undergoes significant swelling upon irradiation, due to the generation of the fission gases.…”

Section: Introductionmentioning

confidence: 99%

“…The effect of these tensile stresses on swelling and creep in the outer fuel zone explains the larger radial than axial swelling and, thus, observed anisotropy in swelling. The outer, anisotropic swelling leads to large radial cracks, presumably because there is insufficient time to relax radial stresses by means of creep [14].…”

Section: Introductionmentioning

confidence: 99%