The objective of this work was to evaluate a new high conductivity nuclear fuel form. Uranium dioxide (UO2) is a very effective nuclear fuel, but it’s performance is limited by its low thermal conductivity. The fuel concept considered here is a ceramic-ceramic composite structure containing UO2 with up to 10 volume percent beryllium oxide (BeO). Beryllium oxide has high thermal conductivity, good neutron moderation properties, neutron production from an (n,2n) reaction, and it is chemically stable with uranium at high temperatures. The UO2-BeO fuel concept employs a continuous lattice of BeO within the microstructure of the fuel in order to significantly increase the thermal conductivity of the fuel. In order to better understand the effect...
Thousands of radiation portal monitors have been deployed worldwide to detect and deter the smugglin...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, February 2005.In...
The radioisotope, technetium-99m (t1/2=6 hours) is used in over 80% of diagnostic medical imaging an...
The objective of this work was to evaluate a new high conductivity nuclear fuel form. Uranium dioxid...
The objective of this work was to continue the evaluation of the high thermal conductivity UO2-BeO (...
The objective of this study was to understand the role of dislocation channeling in the initiation o...
The current US fleet of LWR’s are approaching the end of their original 40 year licenses. Most of th...
A widely used method for Neutronics simulations is MCNP6. Throughout this work, multiple MCNP6 simul...
From the initiation of operations in 1959, the Transient Reactor Test (TREAT) facility at Idaho Nati...
abstract: A distributed-parameter model is developed for a pressurized water reactor (PWR) in order ...
Alloy 617 has been identified as the primary candidate alloy for the intermediate heat exchangers of...
Degradation of structural components in nuclear environments is a limiting factor in the lifetime of...
Traditional powder processes for fabricating plutonium-238 oxide heat source pellets used in radiois...
This study adopts computational fluid dynamics (CFD) to examine fluid dynamics and heat transfer cha...
The objective of this study was to determine the irradiation creep mechanism of FM steel T91 using l...
Thousands of radiation portal monitors have been deployed worldwide to detect and deter the smugglin...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, February 2005.In...
The radioisotope, technetium-99m (t1/2=6 hours) is used in over 80% of diagnostic medical imaging an...
The objective of this work was to evaluate a new high conductivity nuclear fuel form. Uranium dioxid...
The objective of this work was to continue the evaluation of the high thermal conductivity UO2-BeO (...
The objective of this study was to understand the role of dislocation channeling in the initiation o...
The current US fleet of LWR’s are approaching the end of their original 40 year licenses. Most of th...
A widely used method for Neutronics simulations is MCNP6. Throughout this work, multiple MCNP6 simul...
From the initiation of operations in 1959, the Transient Reactor Test (TREAT) facility at Idaho Nati...
abstract: A distributed-parameter model is developed for a pressurized water reactor (PWR) in order ...
Alloy 617 has been identified as the primary candidate alloy for the intermediate heat exchangers of...
Degradation of structural components in nuclear environments is a limiting factor in the lifetime of...
Traditional powder processes for fabricating plutonium-238 oxide heat source pellets used in radiois...
This study adopts computational fluid dynamics (CFD) to examine fluid dynamics and heat transfer cha...
The objective of this study was to determine the irradiation creep mechanism of FM steel T91 using l...
Thousands of radiation portal monitors have been deployed worldwide to detect and deter the smugglin...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, February 2005.In...
The radioisotope, technetium-99m (t1/2=6 hours) is used in over 80% of diagnostic medical imaging an...