C. Bagger et al., TEMPERATURE-MEASUREMENTS IN HIGH BURNUP UO2 NUCLEAR-FUEL - IMPLICATIONS FOR THERMAL-CONDUCTIVITY, GRAIN-GROWTH AND GAS-RELEASE, Journal of nuclear materials, 211(1), 1994, pp. 11-29
Fuel centreline temperatures measured under transient conditions are r
eported. These show that also at burnups as high as 4.5% FIMA the onse
t temperature for thermal gas release is close to 1200-degrees-C. At c
onstant linear power the 1200-degrees-C isotherm moves outwards with b
urnup due to the development of a.thermal barrier at the pellet rim an
d a general degradation in the fuel thermal conductivity. This causes
the observed burnup enhancement of gas release . Using radial temperat
ure profiles constructed from experimental data, grain growth and Xe d
iffusion during a power transient at high burnup are reexamined. It is
found that grain growth is slower than predicted for steady-state irr
adiation conditions. The effective Xe diffusion coefficient, D(We), in
the transient tests with hold times of 40, 42 and 62 h is given by D(
Xe) = 1.9 X 10(-8) exp(- 21890/T) cm2 s-1, T in K. For the tests with
a 4 h hold time, D(Xe) is given by D(Xe) = 2.5 X 10(-9) exp(- 21 0501
T) below 1570-degrees-C, but by the former equation above 1600-degrees
-C. In the long transient tests, the increase in the D(Xe) below 1570-
degrees-C is attributed to the annealing of gas traps in the oxide lat
tice.