a Scientist, Applied Mathematics Division, Vikram Sarabhai Space Centre, Trivandrum 695022, India
b Reader in Applied Mathematics, Institute of Technology, Banaras Hindu University, Varanasi 221005, India
Abstract:
Consideration is made of transient heat transfer in a cylindrical fuel element of the nuclear reactor. The fuel rod, whose power dissipation is assumed to take place in the fuel element by a sinusoidal pulse, and cladding are separated by a thin layer. The conjugate boundary-value problem involving the equation for heat conduction in the fuel rod and cladding, and boundary conditions with regard for non-ideal thermal contact is solved by the Laplace transformation. The results on a temperature distribution for uranium dioxide fuel rod and zirconium cladding when cooled by liquid sodium are presented graphically.