Transport and release of radioactive fission products in nuclear fuels : The new analytical method of the MITRA code
The transport and release of radioactive fission products in nuclear fuels are described with detailed reaction-rate equations including intragranular precipitation, radiation re-solution, biased diffusion, and nuclear transmutations. An analytical procedure to solve these equations makes it possible to calculate the release and redistribution of the radionuclides with greater accuracy and speed than by conventional numerical methods. The method was implemented in the computer code MITRA for the calculation of the radionuclide behaviour during stationary and non-stationary reactor operating conditions. The structure of this code is described, and recalculations of experiments are presented. The analytical solutions of the rate equations are reported.
Bibliographic Reference: Article: Nuclear Science and Engineering, Vol. 107 (1991) pp. 315-329
Record Number: 199110903 / Last updated on: 1994-12-02
Original language: en
Available languages: en