Effect of Dual Surface Cooling on the Temperature Distribution of a Nuclear Fuel Pellet

Abstract:

Heat removal from nuclear reactor core has been one of the major Engineering considerations in the construction of nuclear power plant. At the center of this consideration is the nuclear fuel pellet whose burning efficiency determines the rate of heat transfer to the coolant. This research, focuses on the study of temperature distribution of solid fuel, temperature distribution of annular fuel with external cooling and the temperature distribution of annular fuel with internal and external cooling. We analyzed the different distribution and made a conclusion on the possibility of improving temperature management of Nuclear fuel rod, by designing fuel pellets based on this geometrical and thermal Analysis. To date, a lot of studies has been done on the thermal and geometrical properties of Nuclear fuel pellet, it is observed that annular fuel pellet with simulteneous internal and external cooling can achieve better temperature distribution which leads to high linear heat generation rate, thus generating more power in the design [1]. It has also been observed that annular fuel pellets has low fission gas release [10]. In large LOCA, the peak cladding temperature of annular fuel is about 600 which is significantly less than that of solid fuel (920 ), this is due to the fact that annular fuel cladding has lower initial temperature and the thinner annular fuel can be cooled more efficiently than the solid fuel. One of drawbacks of annular fuel technology is “the fuel gap conductance assymmetry” which is caused by outward thermal expansion, it has a potential effect on the MDNBR (Minimum Departure from Nucleate Boiling Ratio), which is the minimum ratio of the critical to actual heat flux found in the core [10]. In this model, we used the ceramic fuel pellet of UO₂ as our case study. All the parameters in this model are assumed parameters of UO₂. The Heat Transfer tool (ANSYS APDL) was used to validate the Analytical Model of this research.

• Periodical: Key Engineering Materials (Volume 769)
• Pages: 296-310
• DOI: https://doi.org/10.4028/www.scientific.net/KEM.769.296
• Online since: April 2018
• Authors: Odii Christopher Joseph*, Agyekum Ephraim Bonah, Bright Kwame Afornu
• Keywords: Annular, Ansys APDL, Cladding, Cooling, Distribution, DUAL, Flux, Fuel, Gradient, Heat, Inner, MDNBR, Modelling, Nuclear, Outer, Pellet, RADIUS, Thermal

References

[1] N. Todreas and M. Kazimi, Nuclear System, Volume 1 "Thermal Hydraulic Fundamentals,, Maaschussets Institute of Technology (2011).

[2] K. Kruper, steady state in clad nuclear fuel rod in COMSOL,, Rensselaer Polytechnic Institute (2014).

[3] R. Othman, Steady state and transient analysis of heat conduction in nuclear fuel elements,, Masters degree project, KTH-Stockholm Sweden (2004).

[4] P. Hangi, Investigating BWR stability with a new linear frequency domain method and detailed 3-D neutronics.

[5] R.T Lahey and F.J Moody, The thermal hydraulics of Boiling Water Nuclear Reactors, American Nuclear Society (1993).

[6] N. Todreas, M. Kazimi and Franci, Nuclear System elements of thermal hydraulic design,, Maaschussets Institute of Technology (1990).

[7] N. I. Kolev, Nuclear Thermal Hydraulics,, Springer international (2015).

[8] H. Fenech, Heat Transfer and Fluid Flow in Nuclear Systems,, Pergamon Press (1981).

[9] B. Weigand, Analytical Methods for Heat Transfer and Fluid Flow Problems,, Springer Publishing (2004).

[10] M.S Kazimi and P. Hejzlar, "High Performance fuel design for next generation PWRs, final report, Nuclear Energy Research Initiative (NERI] Project 01-005, MIT-NFC-PR-082, January, (2006).