A comparison between fission gas release data and FEMAXI-IV code calculations

Nakajima, Tetsuo; Saito, Hiroaki

doi:10.1016/0029-5493(87)90055-0

Cited by 23 publications

(3 citation statements)

References 8 publications

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“…Urel={Jo, (11) where Urel is the displacement of the finite element radial coordinate of the pellet surface, o the radial pellet cladding gap size at room temperature, f3 the input parameter for the pellet tip relocation and is in the range of 0 to 1. This model is a simplified treatment that corresponds to increasing the pellet diameter and it may give the most severe mechanical interaction.…”

Section: Iron Codementioning

confidence: 99%

Development of LWR Fuel Performance Analysis Codes.

Kinoshita

1993

J. Nucl. Sci. Technol.

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This paper is to cover brief history of the development of LWR fuel performance analysis codes in Japan. This includes the FEMAXI-ill code which calculates local stress and strain of the cladding at power ramp due to the pellet cladding mechanical interaction (PCMI) using axisymmetric finite element method. From this code some improved codes were developed, such as FEMAXI-N, IRON and EIMUS. The FEMAXHV is developed by JAERI to add capacity of transient analysis and the IRON code was developed by Shikoku Electric Power Co. to analyze fuel reliability at load following operation and the EIMUS code was developed by CRIEPI for high burnup analysis. The major objective and contents of adapted submodels in these codes are presented with some calculational results. The future development and utilization of the codes, especially for performance analyses at high burnup, will be briefly discussed.

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Section: Iron Codementioning

confidence: 99%

Development of LWR Fuel Performance Analysis Codes.

Kinoshita

1993

J. Nucl. Sci. Technol.

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“…It is generally accepted that most of the insoluble inert gas atoms Xe and Kr produced during fi ssioning are retained in the fuel irradiated at a temperature lower than the threshold [1][2][3][4][5][6][7][8][9][10]. Some authors [1-3, 5, 7, 9, 10] assume that random diffusion of gas atoms to grain boundaries and consider the effect of trapping the atoms at inter-granular bubbles until saturation occurs.…”

Section: Introductionmentioning

confidence: 99%

Bonding xenon and krypton on the surface of uranium dioxide single crystal

Da̧browski

Szuta

2014

Nukleonika

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Abstract. We present density functional theory (DFT) calculation results of krypton and xenon atoms interaction on the surface of uranium dioxide single crystal. A pseudo-potential approach in the generalised gradient approximation (GGA) was applied using the ABINIT program package. To compute the unit cell parameters, the 25 atom super-cell was chosen. It has been revealed that close to the surface of a potential well is formed for xenon and krypton atom due to its interaction with the atoms of oxygen and uranium. Depth and shape of the well is the subject of ab initio calculations in adiabatic approximation. The calculations were performed both for the case of oxygenic and metallic surfaces. It has been shown that the potential well for the oxygenic surface is deeper than for the metallic surface. The thermal stability of immobilising the atoms of krypton and xenon in the potential wells were evaluated. The results are shown in graphs.

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“…of UO2 grains It is generally accepted that most of the insoluble inert gas atoms of xenon and krypton produced during fissioning are retained in the fuel irradiated at a temperature lower than the threshold [9][10][11][12][13][14][15][16][17]. We assume that most of the gas atoms are retained in the matrix of grains being there immobilised or are precipitated into small fission gas bubbles.…”

Section: Algorithms Of Fission Gas Release Due To Recrystallizationmentioning

confidence: 99%

Modification of Recrystallization Temperature of Uranium Dioxide in Function of Burn-Up and Its Impact on Fission Gas Release

Szuta

El-Koliel

1999

Acta Phys. Pol. A

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In the present paper it is assumed that the recrystallization temperature of uranium dioxide decreases with burn-up. Two opposing effects of enhancement and mhibition of irradiation damage introduced by fission effect on gram growth are described. Mathematical model of fission gas release from the UO 2 fuel affected by grain growth is presented. Theoretical results are compared with the experimental data.

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A comparison between fission gas release data and FEMAXI-IV code calculations

Cited by 23 publications

References 8 publications

Development of LWR Fuel Performance Analysis Codes.

Development of LWR Fuel Performance Analysis Codes.

Bonding xenon and krypton on the surface of uranium dioxide single crystal

Modification of Recrystallization Temperature of Uranium Dioxide in Function of Burn-Up and Its Impact on Fission Gas Release

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