dc.description.abstract |
The effects of change in fuel density, change in clad material and change
in fuel material on the inherent safety features of a typical material test reactor
were analyzed. The International Atomic Energy Agency’s 10 MW benchmark
reactor was selected for the study. Standard computer codes WIMS-D4 and
CITATION were used to perform neutronics calculations while PARET was used
to carryout the steady state and transient thermal hydraulic analysis. In all, seven
thermal hydraulic simulations were performed for each configuration. They were
the steady state analysis, four controlled transients i.e. fast reactivity insertion,
slow reactivity insertion, fast loss of flow and slow loss of flow transients, and two
uncontrolled reactivity insertion transients, i.e. small reactivity insertion and large
reactivity insertion transients.
Two families of the high density dispersion fuels were analyzed to see the
effect of changed uranium density on the inherent safety features of the reactor.
These families were U 3 Si 2 -Al (having uranium densities of 4.10, 4.80 and 5.66
g/cm 3 ) on the lower side and U9Mo-Al (having uranium densities of 6.57, 7.74
and 8.90 g/cm 3 ) on the upper side. It was observed that the steady state
thermodynamic behaviour of all the fuels was same, only the fuel temperatures of
U 3 Si 2 -Al fuels showed some differences. During the fast reactivity insertion
transient, the maximum reactor power achieved increased by about 29% for
U 3 Si 2 fuel-family while the increase was 45% for U9Mo fuel-family. This resulted
in increased maximum temperatures of fuel, clad and coolant outlet, achieved
during the transient. This increase for U 3 Si 2 fuels was 32 K, 21.1 K and 5.1 K
respectively, while for U9Mo fuels it was 27.7 K, 19.7 K and 7.9 K respectively for
maximum fuel, clad and coolant outlet temperatures. During the slow reactivity
insertion and loss of flow transients, no appreciable difference in the reactor
power and temperature profiles was observed. For small reactivity insertion
transient, the new power level increased as uranium density increased. The
increase was 8.1% for U 3 Si 2 fuel-family while it was 5.8% for U9Mo fuel-family. In
uncontrolled large reactivity insertion transient, the feedback reactivities were
unable to control the reactor which resulted in the coolant boiling; the one with
the highest fuel density was the first to reach the ONB.
xxviiIn order to see the effects of different fuel materials, the original aluminide
(UAl x -Al) fuel of the reactor was replaced with silicide (U 3 Si-Al and U 3 Si 2 -Al) and
oxide (U 3 O 8 -Al) dispersion fuels having the same uranium density of 4.40 g/cm 3
as of the original fuel. The oxide fuel had higher fuel temperatures during steady
state and transients. During fast reactivity insertion transient, the maximum
power reached for oxide fuel was 0.35 MW lesser than that of aluminide fuel, but
its maximum fuel temperature was 13 K higher. With respect to the UAl x -Al fuel,
the maximum powers of U 3 Si-Al and U 3 Si 2 -Al fuels were higher by 2.11 MW and
1.82 MW respectively, while the maximum fuel temperatures were lower by 5.7 K
and 4.5 K respectively. During slow reactivity insertion and loss of flow transients,
the power and temperature profiles of all the fuels were almost the same only
fuel temperatures varying; the maximum fuel temperature of the oxide fuel being
8 K to 12 K higher than that of the other fuels. During uncontrolled small reactivity
insertion transient, the maximum fuel temperature attained by the oxide fuel was
almost 16 K higher than that of the others at the new steady state. During
uncontrolled large reactivity insertion transient, the coolant of oxide fuel was the
last to reach the ONB but again at the cost of higher fuel temperature.
In order to see the effects of different clad materials, only the Al clad and
side plates of the reactor fuel were replaced by stainless steel (clad of a fast
reactor) and zircaloy-4 (clad of a PWR). The zircaloy-4 clad gave a positive clad
temperature feedback coefficient. The very high absorption cross section of
stainless steel made it a very unlikely choice for clad material. Out of the
remaining two, the main difference was in the fuel temperatures with zircaloy-4
cladded fuel having higher fuel temperatures. The temperature of zircaloy-4
cladded fuel was 20 K to 40 K higher than that of Al cladded fuel during different
transients. |
en_US |