Fabrication of plutonium containing fuels through the internal gelation method has mostly been studied in mixed metal systems such as U, Pu or Zr, Pu. In this work production of undiluted PuN has been performed by carbothermal reduction on both oxide powder and Pu microspheres produced by the internal gelation method. Nitride purities reached using the different methods have been studied together with final densities achieved during pellet fabrication as well as losses of ingrown Am during the different production steps. Formation of Pu microspheres was successfully performed using the internal gelation method, although extensive microsphere fracturing occurred during thermal treatment. Final densities of PuN pellets produced by cold pressi...
Additional work on the synthesis and fabrication of uranium nitride produced an improved product fre...
Composites of actinide oxides dispersed in a Mo metal matrix is a recent inert matrix fuel (IMF) con...
Uranium mononitride (UN) is a candidate fuel material for light water reactors with higher uranium (...
Sol-gel based techniques are one way to lower the handling of highly radioactive powders when produc...
At the heart of a nuclear reactor resides its fuel. The chemical composition of the nuclear fuel aff...
Nitride fuels have been regarded as one viable fuel option for Generation IV reactors due to their p...
The main objective of this master thesis was assessing and evaluating the production of mixed U-Zr n...
The main objective of this master thesis was assessing and evaluating the production of mixed U-Zr n...
AbstractDuring operation of a fourth generation reactor system it is necessarily not desirable to ut...
The future of nuclear energy in the U.S. and its expansion worldwide depends greatly on our ability ...
In this study, the process involved in the fabrication of a potential accident tolerant fuel is desc...
The hot-pressing characteristics of mixed (U,Pu)N for advanced reactor fuel were studied in order to...
Pacific Northwest Laboratory (PNL) has evaluted, on a laboratory scale, the characteristics and pell...
(U0.45Pu0.55)N and (U0.8Pu0.2)N are being considered in India as advanced alternative fuels for the ...
Mixed depleted UO{sub 2} and PuO{sub 2} (MOX) pellets prototypic of fuel proposed for use in commerc...
Additional work on the synthesis and fabrication of uranium nitride produced an improved product fre...
Composites of actinide oxides dispersed in a Mo metal matrix is a recent inert matrix fuel (IMF) con...
Uranium mononitride (UN) is a candidate fuel material for light water reactors with higher uranium (...
Sol-gel based techniques are one way to lower the handling of highly radioactive powders when produc...
At the heart of a nuclear reactor resides its fuel. The chemical composition of the nuclear fuel aff...
Nitride fuels have been regarded as one viable fuel option for Generation IV reactors due to their p...
The main objective of this master thesis was assessing and evaluating the production of mixed U-Zr n...
The main objective of this master thesis was assessing and evaluating the production of mixed U-Zr n...
AbstractDuring operation of a fourth generation reactor system it is necessarily not desirable to ut...
The future of nuclear energy in the U.S. and its expansion worldwide depends greatly on our ability ...
In this study, the process involved in the fabrication of a potential accident tolerant fuel is desc...
The hot-pressing characteristics of mixed (U,Pu)N for advanced reactor fuel were studied in order to...
Pacific Northwest Laboratory (PNL) has evaluted, on a laboratory scale, the characteristics and pell...
(U0.45Pu0.55)N and (U0.8Pu0.2)N are being considered in India as advanced alternative fuels for the ...
Mixed depleted UO{sub 2} and PuO{sub 2} (MOX) pellets prototypic of fuel proposed for use in commerc...
Additional work on the synthesis and fabrication of uranium nitride produced an improved product fre...
Composites of actinide oxides dispersed in a Mo metal matrix is a recent inert matrix fuel (IMF) con...
Uranium mononitride (UN) is a candidate fuel material for light water reactors with higher uranium (...