Mitra : An advanced code to calculate radionuclide release from nuclear fuels under general irradiation conditions
The paper presents the computer code Mitra (Multicomponent isotope transport) which has been constructed to calculate the release of radioactive fission products from nuclear fuels under non-stationary conditions. The code is based on a new integration of the mass transport equation in the presence of precipitation, re-solution and radioactive decay. The starting equations and the assumed physical models are briefly described in the main part of the report. A very detailed description of the formulae used and of the Mitra subprograms are presented in extended appendices.
Bibliographic Reference: EUR 12375 EN (1989) FS, 68 pp., ECU 6.25
ISBN: ISBN 92-826-0837-9;CD-NA-
Record Number: 198911240 / Last updated on: 1994-12-01
Original language: en
Available languages: en