Modelling the high burnup UO2 structure in LWR fuel

Laßmann, K.; Walker, C.T.; Laar, J. van de; Lindstrom, F. T.

doi:10.1016/0022-3115(95)00116-6

Cited by 114 publications

(73 citation statements)

References 15 publications

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“…Lassmann et al (1994) from the Institute for Transuranium Elements, Karlsruhe, Germany, wrote the TUBRNP code, which improves upon RADAR by modifying the parameters for the plutoniumdistribution function and accounting for the plutonium isotopes explicitly. The result is a somewhat more edge-peaked distribution function at nominal to high fuel burnups, which is supported by comparison to detailed neutronics calculations and to detailed electron microprobe data on the distribution of both plutonium and stable fission products (Lassmann et al 1994;Lassmann et al 1995). Lassmann's model has demonstrated good comparisons to detailed data on burnup distribution while retaining more generality than the specific-case interpolations by Matsamura or Shann; it is therefore chosen for application in FRAPCON-3.…”

Section: Introductionmentioning

confidence: 83%

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

Lanning¹,

Beyer²,

Painter³

1997

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Section: Introductionmentioning

confidence: 83%

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

Lanning¹,

Beyer²,

Painter³

1997

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“…For power reactors burn-up is expressed as the cumulative heat output from a nuclear fuel, i.e., in megawatt days per kilogram heavy metal (U + Pu). The rare-earth fission product neodymium can be used as an indicator of the local burn-up because it is immobile in the fuel [21]. (The neodymium nuclide remains in the lattice site where it comes to rest following fission.)…”

Section: Determination Of the Local Burn-up In Irradiated Nuclear Fuelmentioning

confidence: 99%

“…[28]). EPMA has revealed that when re-crystallisation occurs nearly all the fission gas is swept out of the fuel matrix [21]. Consequently, the radial extent of re-crystallisation, and the burn-up and temperature thresholds for the process can be established from the distance over which xenon depletion occurs (figure 7) [29].…”

Section: Re-crystallisation Of Nuclear Fuel At High Burn-upmentioning

confidence: 99%

Microbeam analysis of irradiated nuclear fuel

Walker¹,

Stephan²,

Pöml³

et al. 2012

IOP Conf. Ser.: Mater. Sci. Eng.

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Abstract. Microbeam analysis is widely used in the nuclear power industry. It is used to characterise the as-fabricated fuel, for routine post-irradiated examination and for research into the mechanisms of phenomena that limit the energy production of the fuel. The techniques most commonly used are wavelength-dispersive electron probe microanalysis, scanning electron microscopy and secondary ion mass spectrometry. Other microbeam analysis techniques that have been successfully applied to irradiated nuclear fuel are transmission and replica electron microscopy, X-ray fluorescence and micro X.-ray diffraction. Specific examples illustrating the past and present use of microbeam analysis in nuclear research establishments are presented with emphasis on the unique results they provide. As an aid to understanding, some basic facts about nuclear fuel rods and their irradiation are first given. This is followed by a description of features that set apart the microbeam analysis of high radioactive materials from standard practice.

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“…E x p er i m ent a l d at a p r e sent ed i n t h e l i t erat u re The onset of the gra i n subdi vi sion pro cess i s observed at a burn-up appro xi m atel y fro m 60 MW d / kgU to 75 MW d/ kg U [2].…”

mentioning

confidence: 99%

“…It has b een conÙrm ed by num erous m easurem ents p erform ed by el ectro n pro be m i croanalysi s (EPMA) tha t xenon depl eti on of the m atri x occurs, due to atherm al rel ease o f xenon fro m the UO 2 gra i ns [1,2,4]. The experi m enta l resul ts i ndi cate tha t nearl y a ll xeno n tha t has b een swept out of the ori gi nal gra ins i s conta i ned i n the newl y form ed Ùssi o n gas p ores [2,5,6].…”

mentioning

confidence: 99%