Computer modeling of steady state fission gas behavior in carbide fuels

Abstract A model for the simulation of long-term, steady-state fission gas behavior in carbide fuels is formulated. It is assumed that fission gas release occurs entirely through gas atom diffusion to grain boundaries and cracks. Fission gas bubbles are assumed to remain stationary and to grow as the net result of gas atom precipitation into the bubbles from the matrix solid and gas atom re-solution from the bubbles into the matrix. Furthermore, assuming that local gas atom redistribution process in the immediate neighborhood of a bubble is very rapid, the bubble size is assumed to correspond to the equilibrium size that maintains exact balance between the rate of gas atom re-solution and that of gas atom precipitation. The model also treats the effect of attachment between bubbles and second-phase precipitates; the experimentally observed faster growth rate of precipitate bubbles is simulated using a reduced re-solution parameter for precipitate bubbles. With the grain matrix assumed to be spherical, the model allows the computation of the radial distribution of the intragranular bubbles and the gas atom concentration in the matrix. The flux of gas atoms arriving at the grain boundary is computed. The continual growth of grain boundary bubbles, resulting from the accumulation of gas atoms on the grain boundary, leads to grain boundary interlinkage and all gas atoms that subsequently reach the grain boundary are assumed to be released. Similarly, all gas atoms generated following the interlinkage of intragranular bubbles are also assumed to be immediately released. Application of the model indicates that fission gas swelling is largely due to intragranular bubbles. Grain boundary bubbles, although very large in size, contribute little to fission gas swelling and the contribution from gas atoms in solid solution in the matrix is even less significant. Physical parameters entering the model were assigned numerical values that closely represent the physical characteristics of the irradiation samples. Careful comparisons between the results of sensitivity studies and the experimental data readily identify the re-solution parameter to have the strongest influence on the results predicted by the code and that the grain size, and not the temperature, is the dominant factor affecting gas release. When allowance is made for the uncertainties of the experimental data, the predicted fission gas swelling also correlates well with experiment. The spread in the fuel swelling data, however, indicates that fuel cracking, and not fission gas swelling alone, very often contributes significantly to the fuel external dimensional changes. The linear fission gas swelling rate prediceted by the model exhibits almost a linear variation with temperature. This result correlates well with the linear swelling rate obtained from experimental swelling data if immersion density data alone are used, in order to eliminate the sources of uncertainties associated with fuel cracking.

[1]  M. Speight Letter to the editors — lettres aux redacteursA calculation on the size distribution of intragranular bubbles in irradiated UO2 , 1971 .

[2]  J. Turnbull,et al.  Observations demonstrating the re-solution of gas from bubbles and sintering pores during the irradiation of UO2 at a high temperature , 1970 .

[3]  R. M. Cornell,et al.  An electron microscope examination of matrix fission-gas bubbles in irradiated uranium dioxide , 1971 .

[4]  R. Hammond,et al.  Superconducting Properties of Nb3 (Al, Ge) Prepared by Vacuum Vapor Deposition of the Elements , 1972 .

[5]  M. V. Speight,et al.  A Calculation on the Migration of Fission Gas in Material Exhibiting Precipitation and Re-solution of Gas Atoms Under Irradiation , 1969 .

[6]  H. Shaked Diffusion of Xenon in Uranium Monocarbide. , 1962 .

[7]  G. W. Greenwood,et al.  An analysis of the diffusion of fission gas bubbles and its effect on the behaviour of reactor fuels , 1963 .

[8]  G. W. Greenwood,et al.  The role of vacancies and dislocations in the nucleation and growth of gas bubbles in irradiated fissile material , 1959 .

[9]  M. Speight Bubble diffusion and coalescence during the heat treatment of materials containing irradiation-induced gases , 1964 .

[10]  R. S. Nelson The stability of gas bubbles in an irradiation environment , 1969 .

[11]  F. A. Nichols,et al.  Kinetics of diffusional motion of pores in solids: A review , 1969 .

[12]  J. Turnbull,et al.  The re-solution of fission-gas atoms from bubbles during the irradiation of UO2 at an elevated temperature , 1971 .

[13]  M. Speight An Analysis of Bubble Growth in Materials Supersaturated with Inert Gas , 1968 .

[14]  A. Brailsford,et al.  Growth of Grain-Boundary Precipitates , 1969 .

[15]  Frank S. Ham,et al.  Theory of diffusion-limited precipitation , 1958 .

[16]  J. Turnbull,et al.  The re-solution of gas atoms from bubbles during the irradiation of UO2 , 1970 .

[17]  R. Barnes A theory of swelling and gas release for reactor materials , 1964 .

[18]  A. J. Markworth Growth of inert-gas bubbles in solids; behaviour of non-uniform size distributions , 1972 .

[19]  A. J. Markworth On the binding between gas bubbles and grain boundaries , 1970 .

[20]  A. J. Markworth Growth of Inert-Gas Bubbles in Solids with Constant Rate of Gas Generation , 1969 .

[21]  R. S. Nelson On the binding of inert gas bubbles to precipitates , 1966 .

[22]  A. J. Markworth Growth Kinetics of Inert‐Gas Bubbles in Polycrystalline Solids , 1972 .

[23]  R. W. Weeks,et al.  LIFE-II: A COMPUTER ANALYSIS OF FAST-REACTOR FUEL-ELEMENT BEHAVIOR AS A FUNCTION OF REACTOR OPERATING HISTORY. , 1972 .

[24]  C. Dollins Fission gas swelling and long-range migration at low temperatures , 1973 .

[25]  C. Ronchi,et al.  Calculations on the in-pile behavior of fission gas in oxide fuels , 1971 .

[26]  E. E. Gruber Calculated Size Distributions for Gas Bubble Migration and Coalescence in Solids , 1967 .

[27]  R. S. Nelson The influence of irradiation on the nucleation of gas bubbles in reactor fuels , 1968 .