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Current Trends in Science and Technology

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Engineering and Technology

Optimization of Nuclear Fuel Pellet by Thermal and Structural Analysis

Naykodi Ganesh Dnyaneshwar, Mathe Raviraj Vikas,Arote Sameer Pandurang, NavaleVipul R.
NavaleVipul R.4 1,2,3 UG Student, Dept. of Mechanical Engineering, Jaihind College of Engineering, Kuran,Pune 4Professor, Dept. of Mechanical Engineering, Jaihind College of Engineering, Kuran,Pune Email Id: 1naykodiganesh16@gmail.com 2matheraviraj1@gmail.com 3samirarote@gmail.com
Online First: February 15, 2018
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Abstract

It is essential to designing and preventing the failure of fuel pellet in operating conditions to predicts the thermo-mechanical Performance of fuel pellet in nuclear reactor. In this paper, the structural analysis taken for fuel elements in operating parameters of nuclear reactor. For performing this analysis firstly, the thermal analysis of fuel pellet is taken to get the unsteady temperature distribution in the fuel pellet and after that these thermal loads are utilized in the structural analysis.


By performing this analysis, the displacement stress and strain values of fuel pellet are find out for gap thickness in the cladding and pellet surface from structural analysis, it is known that expansion due to thermal effectuations and it’s within limit.


For cladding and pellet, the governed equations are considered and the physical and thermal properties are considered while taking analysis the height of fuel element is greater than the outer diameter of fuel element rod. So the axially temperature variation is not considered within analysis so there is 1-d heat transfer equation formation.


So far for this analysis, a finite element method is used, ANSYS is used to discretization as Computational Domain. The combined analysis of fuel element is taken out for finding temperature thermal expansions, heat fluxes generation and the stress-strain parameters..

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Feb 15, 2018
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Feb 15, 2018
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References

[1] ANSYS. [2] M. Dostal, A Krupkin, “3D modelling of VVER fuel pellet cracking during power ramp” [3] Fernando Pereira, Jean Salome., “Thermal Analsys of spent Nuclear fuels Repository”, 5th international ATELANTE Conference on nuclear chemistry for sustainable fuel cycles, Procedia Chemistry 21 (2016) 386-393 [4] Su Chaing shu Faya,”A Survey on Fuel Pellet Cracking and Healing Phenomena in Reactor Operation.” INFORMA CAO IPEN-9 OUTRBO/1981 [5] Marchal, N., Campos, C., Garnier, C. Finite element simulation of pellet cladding interaction in nuclear fuel rodes, computational material Science vol. 45 page 821-826, 2009 [6] Young-Doo Kwon and Bo-Kyoung Shim,“Thermo-Mechanical Analysis of Annular Pellet Nuclear Fuel and Its Comparison with Solid and Annular Nuclear Fuel Types” International Journal of Applied Engineering Research ISSN 0973-4562 Volume 11, Number 21 (2016) pp.10543-1055.
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References

[1] ANSYS.
[2] M. Dostal, A Krupkin, “3D modelling of VVER fuel pellet cracking during power ramp”
[3] Fernando Pereira, Jean Salome., “Thermal Analsys of spent Nuclear fuels Repository”, 5th international ATELANTE Conference on nuclear chemistry for sustainable fuel cycles, Procedia Chemistry 21 (2016) 386-393
[4] Su Chaing shu Faya,”A Survey on Fuel Pellet Cracking and Healing Phenomena in Reactor Operation.” INFORMA CAO IPEN-9 OUTRBO/1981
[5] Marchal, N., Campos, C., Garnier, C. Finite element simulation of pellet cladding interaction in nuclear fuel rodes, computational material Science vol. 45 page 821-826, 2009
[6] Young-Doo Kwon and Bo-Kyoung Shim,“Thermo-Mechanical Analysis of Annular Pellet Nuclear Fuel and Its Comparison with Solid and Annular Nuclear Fuel Types” International Journal of Applied Engineering Research ISSN 0973-4562 Volume 11, Number 21 (2016) pp.10543-1055.
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