Add to ORKGThe Wigner-Seitz pin-cell approximation has long been applied as a modeling approximation in analysis of UO2 lattice fuel cells. In the past, this approximation has been appropriate for such fuel. However, with increasing attention drawn to mixed-oxide (MOX) fuels with significant plutonium content, it is important to understand the implications of the approximation in a uranium-plutonium matrix. The special geometric capabilities of the deterministic NEWT computer code have been used to assess the adequacy of the Wigner-Seitz cell in such an environment, as part of a larger study of computational aspects of MOX fuel modeling. Results of calculations using various approximations and boundary conditions are presented, and are validated by co...
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997.Includes b...
Thorium-plutonium Mixed OXide fuel (Th-MOX) is considered for use as light water reactor fuel. Both ...
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Cent...
The submitted manuscript has been authored by a contractor of the U.S. Governmen
An empirical potential study was performed for the americium (Am), neptunium (Np) containing uranium...
NEUTRONIC CALCULATION FOR PWR MOX FUEL PIN CELLS WITH WIMSD-5B CODE. The WIMSD-5B thermal reactor la...
A comparative analysis and comparison of results obtained between 2-D lattice calculations and 3-D f...
International audienceA dynamic fuel cycle simulation code models all the ingoing and outgoing mater...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012...
Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light...
The prediction of fuel rod behaviour in a Light Water Reactor at high bumup is difficult because the...
One possible method to reduce the enrichment of the surplus of weapons-grade plutonium is to irradia...
With the aim of generating a certain feeling for the general dependencies of the multiplication fact...
Fundamental understanding of the behaviour of nuclear fuel has been of great importance. Enhancing t...
International audienceThe molecular Monte Carlo method, combined with the CRG interatomic potential,...
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997.Includes b...
Thorium-plutonium Mixed OXide fuel (Th-MOX) is considered for use as light water reactor fuel. Both ...
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Cent...
The submitted manuscript has been authored by a contractor of the U.S. Governmen
An empirical potential study was performed for the americium (Am), neptunium (Np) containing uranium...
NEUTRONIC CALCULATION FOR PWR MOX FUEL PIN CELLS WITH WIMSD-5B CODE. The WIMSD-5B thermal reactor la...
A comparative analysis and comparison of results obtained between 2-D lattice calculations and 3-D f...
International audienceA dynamic fuel cycle simulation code models all the ingoing and outgoing mater...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2012...
Both the Russian Federation and the US are pursing mixed uranium-plutonium oxide (MOX) fuel in light...
The prediction of fuel rod behaviour in a Light Water Reactor at high bumup is difficult because the...
One possible method to reduce the enrichment of the surplus of weapons-grade plutonium is to irradia...
With the aim of generating a certain feeling for the general dependencies of the multiplication fact...
Fundamental understanding of the behaviour of nuclear fuel has been of great importance. Enhancing t...
International audienceThe molecular Monte Carlo method, combined with the CRG interatomic potential,...
Thesis (Ph.D.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1997.Includes b...
Thorium-plutonium Mixed OXide fuel (Th-MOX) is considered for use as light water reactor fuel. Both ...
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Cent...