Current research on the topic of advanced reactor fuel types include the use of ultrahigh density Uranium-Molybdenum fuels, towards their use in high-performance research reactors. These reactors operate with high power densities, and the increased cooling requirements therefore place high relevance on the fluid-structure interaction with these fuel elements; therefore...
In order to properly model the temperature distribution of a nuclear fuel pin, the thermal conductivity
of the fuel must be known. For sphere pac fuel, the
modeling of the conductivity is complicated due to the
fact that the fuel is a collection of spheres in a random packed bed....
The use of advanced concepts can make the nuclear fuel
cycle more efficient by allowing pins to be operated at
high powers and to higher burnups. Among the more
promising concepts in advanced fuels is sphere pac fuel.
In a first attempt to bring together models describing
individual phenomena, the...
The establishment of any thermal model of reactor fuel
requires a thorough understanding of the behavior of the
thermal conductivity. This is especially true in the case
of sphere pac fuels where the conductivity is a function
of many variables beyond those normally affecting conventional
fuels. One of these variables,...
With the advent of next generation reactor systems and new fuel designs, the U.S. Department of Energy (DOE) has identified the need for the resumption of transient testing of nuclear fuels. The DOE has decided that the Transient Reactor Test Facility (TREAT) at Idaho National Laboratory (INL) is best suited...
The Boltzmann transport equation derived in the Self-Adjoint Angular Flux (SAAF) formulation is applied to simulate phonon transport. The neutron transport code Rattlesnake is leveraged in this fashion, slightly modi ed to accept input from variables consistent with phonon transport simulations. Several benchmark problems are modeled to assess the potential...
Fuel loading patterns which have a minimum power peak are
economically desirable to allow power reactors to operate at the highest
possible power density and to minimize the possibility of fuel
failure. A computer code called SHUFLE was developed for pressurized
water reactors which shuffles the fuel in search of...
Because of the high cost of fuel for nuclear reactors, fuel cycle
costs must be predicted accurately.
This leads to the high cost computer computations and a search for cheaper yet still accurate
methods. For this paper we have chosen to study an alternate
method for calculating thermal neutron cell...
Lattice bum-up calculations in thermal reactors are complicated by the necessity
for use of transport theory to represent fuel rods, control rods, and burnable absorbers,
by many time-dependent variables which must be considered in the analysis, and by
geometric complexity which introduces time-dependent, spatial-spectral variations.
Representation of lattice structure in...