Development and Irradiation Performance of Uranium Aluminide Fuels in Test Reactors

Beeston, J.M.; Hobbins, R.R.; Gibson, G.W.; Francis, W.C.

doi:10.13182/nt80-a32515

Cited by 29 publications

(16 citation statements)

References 22 publications

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“…The release will increase upon reaching the solidus temperature of the cladding and at the U-Al eutectic temperature [21][22][23][24]. For the fuel plates under consideration this would be respectively, 565°C (blistering temperature), about Fig.…”

Section: Discussionmentioning

confidence: 99%

Microstructural analysis of MTR fuel plates damaged by a coolant flow blockage

Leenaers

Joppen

Berghe

2009

Journal of Nuclear Materials

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Section: Discussionmentioning

confidence: 99%

Microstructural analysis of MTR fuel plates damaged by a coolant flow blockage

Leenaers

Joppen

Berghe

2009

Journal of Nuclear Materials

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“…. These values are much lower than the measured blister threshold temperature of 480 o C (896 o F) for the aluminide fuel [10]. As expected, the lower step reactivity insertions of 0.0025 Δk/k and 0.001 Δk/k result in much lower peak power bursts and peak fuel and clad surface temperatures.…”

Section: Anl/gtri/tm-13/7mentioning

confidence: 50%

Preliminary Accident Analyses for Conversion of the University of Missouri Research Reactor (MURR) from Highly-Enriched to Low-Enriched Uranium Prepared by

Feldman¹,

Foyto²,

Kutikkad³

et al. 2013

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“…It is well known that excessive fuel meat temperature in plate type fuel can lead to thermally induced blistering 10,11 like that observed on the AFIP-6A fuel plate and that these blisters can rupture and release fission gases into the primary coolant system. It is also known that the rate of oxide formation on aluminum surfaces is strongly coupled to the fuel plate surface temperature.…”

Section: Experiments Analysismentioning

confidence: 99%

AFIP-6 Breach Assessment Report

Wachs¹,

Robinson²,

Medvedev³

2011

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Analysis of the AFIP-6 experiment is summarized in this report in order to determine the cause of gaseous fission product release observed during irradiation. During the irradiation, a series of small fission product releases were observed. In order to limit the potential for primary coolant contamination, the operating cycle was terminated and the AFIP-6 experiment was removed for examination. Both in-canal and post-irradiation examination revealed the presence of an unusually thick oxide layer and discrete surface blisters on the fuel plates. These blisters were the likely cause of fission product release.Subsequent detailed thermal hydraulic analysis of the experiment indicated that the combination of the high operating power and test vehicle configuration led to high nominal operating temperatures for the fuel plates. This elevated temperature led to accelerated surface corrosion and eventually spallation of the fuel plate cladding. The thermal insulating nature of this corrosion layer led to significantly elevated fuel meat temperatures that induced blistering.Analysis was performed to validate a corrosion rate model and criteria for onset of spallation type surface corrosion were determined. The corrosion rate model will be used to estimate the oxide thickness anticipated for experiments in the future. The margin to the spallation threshold will then be used to project the experiment performance. vi vii CONTENTS

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Development and Irradiation Performance of Uranium Aluminide Fuels in Test Reactors

Cited by 29 publications

References 22 publications

Microstructural analysis of MTR fuel plates damaged by a coolant flow blockage

Microstructural analysis of MTR fuel plates damaged by a coolant flow blockage

Preliminary Accident Analyses for Conversion of the University of Missouri Research Reactor (MURR) from Highly-Enriched to Low-Enriched Uranium Prepared by

AFIP-6 Breach Assessment Report

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