Fuel-to-cladding gap evolution and its impact on thermal performance of high burnup fast reactor type uranium–plutonium oxide fuel pins

Inoue, Masakí; Maeda, Koji; Katsuyama, Kozo; Tanaka, Kosuke; Mondo, Kenji; Hisada, Masaki

doi:10.1016/j.jnucmat.2003.12.015

Cited by 29 publications

(16 citation statements)

References 11 publications

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“…Due to excessive stresses generated with the diffusion of cesium and molybdenum, localized trans-granular fracture of the fuel, as-fabricated porosity shrinkage and significant release of fission gases were reported in Ref. [14]. Furthermore, Ref.…”

Section: Fuel Chemistry and Restructuringmentioning

confidence: 99%

“…The formation of JOG and resulting intense diffusion of fission products and internal stresses generated in the fuel results in trans-granular cracking of the grains. Hence, reduced grain size may lead to a higher fission gas release rate at the brittle peripheral region of the fuel [14]. To account for the effect of JOG on the fission gas release, the temperature independent part of the gas diffusion coefficient (second term in the bracket in Eq.…”

Section: Gas Diffusion Coefficientmentioning

confidence: 99%

“…JOG formation starts with the availability of excess oxygen (oxygen-to-metal ratio is above 1.985) around 2 at% burnup. As a consequence, fission gas release increases significantly due to trans-granular fracture and resulting decrease in effective grain size [14]. This behavior is modeled by increasing the fission-enhanced gas diffusion coefficient (Equation-2).…”

Section: Isothermal Fission Gas Release Benchmarksmentioning

confidence: 99%

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Modeling of thermo-mechanical and irradiation behavior of mixed oxide fuel for sodium fast reactors

Karahan

Buongiorno

2010

Journal of Nuclear Materials

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Section: Fuel Chemistry and Restructuringmentioning

confidence: 99%

Section: Gas Diffusion Coefficientmentioning

confidence: 99%

Section: Isothermal Fission Gas Release Benchmarksmentioning

confidence: 99%

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Modeling of thermo-mechanical and irradiation behavior of mixed oxide fuel for sodium fast reactors

Karahan

Buongiorno

2010

Journal of Nuclear Materials

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“…In the previous analysis code, the central void size was determined from two radial distributions of CT values measured at two orthogonal directions shown in Figure 2 (a) by the method already reported in the previous paper [3,4], assuming that the central void is circular and exists at the radial center of pellet. But the deviation of central void position from the radial center of fuel pellet and the existence of radial cracks evolved during power increase in the operation were not taken into considerations.…”

Section: Improvements In the Analysis Code Of X-ray Ct Imagesmentioning

confidence: 99%

“…Conventional post irradiation examinations (PIEs) give results on fuel rod performance after dismantling the fuel assembly [2,3], but X-ray CT technology has a great merit of being able to examine the fuel rods performance in the intact fuel assembly.…”

Section: Introductionmentioning

confidence: 99%

Upgrading of X-ray CT technology for analyses of irradiated FBR MOX fuel

Ishimi

Katsuyama

Maeda

et al. 2012

Journal of Nuclear Science and Technology

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The X-ray CT technology previously developed by JAEA was upgraded. The shape of the X-ray source beam was changed from a circular shape to an elliptical one and the collimator slit width was decreased from 0.3 to 0.1 mm. The X-ray detector was improved by changing a CdWO 4 scintillator to a highly sensitive silicon semiconductor detector. The analysis code of X-ray CT image was revised with respect to the number of points by using two kinds of experimental results and taking into account the effects of crack existence and deviation of the central void position from the radial center of a fuel pellet. As a result, high resolution X-ray CT images could be obtained on the transverse cross section of irradiated fuel assemblies. The error of the dimensional measurement was improved from +0.1 to +0.03 mm by upgrading the instrument and revising the analysis code of X-ray CT image. The discriminating accuracy of density difference could be increased, and the low density region (undisturbed region) and high density region (equi-axial and columnar regions) in the X-ray CT image on the cross section of irradiated fuel could be discriminated from each other. The reliability of fuel performance analysis improves because a large number of PIE data can be collected, compared with the conventional destructive PIE.Keywords: post-irradiation examination; X-ray CT; fast breeder reactor; irradiated nuclear fuel IntroductionThe Japan Atomic Energy Agency (JAEA) has been continuing the development of X-ray CT technology to investigate the performance of irradiated fast breeder reactor (FBR) MOX fuel [1]. Conventional post irradiation examinations (PIEs) give results on fuel rod performance after dismantling the fuel assembly [2,3], but X-ray CT technology has a great merit of being able to examine the fuel rods performance in the intact fuel assembly.Previously two-dimensional X-ray CT images on a number of transverse cross-sections have been obtained for irradiated fuel assemblies. From these images the deformations of fuel rods along the axial direction within the fuel assemblies were dimensionally investigated [4,5]. Next, the sizes of central voids formed in the fuel pellets by a steep temperature gradient were roughly measured and the relationship between the void sizes and linear heat rating was discussed [5,6]. In addition, two-dimensional X-ray CT images were synthesized to get three-dimensional X-ray CT images [7,8], and it was demonstrated as being

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