论文信息 - The oxired model for redistribution of oxygen in nonstoichiometric uranium-plutonium oxides

The oxired model for redistribution of oxygen in nonstoichiometric uranium-plutonium oxides

Abstract The oxygen distribution model OXIRED is described which predicts the steady-state and transient radial oxygen-to-metal ratios in a fuel rod as a function of the average burnup, the radial temperature profile and the time for hyperstoichiometric oxides UO 2 + x (LWR conditions) and hypostoichiometric mixed oxides (U 1−q Pu q )O 2−x (FBR conditions). Numerous calculations with the fuel rod performance code TRANSURANUS into which the OXIRED model has been incorporated have proven that the newly developed numerical algorithm is extremely fast and reliable.

K. Lassmann

[1] M. Mogensen,et al. On the Rate Determining Step in Fission Gas Release from High Burn-up Water Reactor Fuel during Power Transients , 1987 .

[2] H. Kleykamp,et al. The chemical state of the fission products in oxide fuels , 1985 .

[3] J. H. Davies,et al. The chemical effects of composition changes in irradiated oxide fuel materials , 1971 .

[4] Hj. Matvke. Diffusion processes in nuclear fuels , 1986 .

[5] K. Lassmann,et al. URANUS — A computer programme for the thermal and mechanical analysis of the fuel rods in a nuclear reactor , 1978 .

[6] Donald R. Olander,et al. Fundamental Aspects of Nuclear Reactor Fuel Elements , 1976 .

[7] H. Matzke,et al. Oxygen potential measurements in irradiated mixed oxide fuel , 1984 .

[8] C. Sari,et al. Oxygen redistribution in fast reactor oxide fuel , 1976 .

[9] H. Kleykamp. The chemical state of LWR high-power rods under irradiation , 1979 .