The objective of this work was to continue the evaluation of the high thermal conductivity UO2-BeO (UBO) nuclear fuel. Current ceramic UO2 fuel offers many fuel performance benefits, but it has a low thermal conductivity. This results in high operating fuel temperatures, but this is a well-excepted performance compromise. Addition of Beryllium oxide to the fuel structure has been shown to increase the fuel thermal conductivity and provide positive neutronic benefits. Pellet heat conduction studies were performed at different linear heat generation rates (LHGR). At an average LHGR of 163.4 W/cm, UBO 10vol% fuel showed a decrease of 74 and 166 degrees C in the effective and centerline temperature, respectively. Similarly at a peak LHGR of 5...
Pool boiling is an effective method used in many technical applications for a long time. Its highly ...
The threshold-fission (fertile) nature of Am-241 is used to destroy this minor actinide by capitaliz...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2010...
The objective of this work was to evaluate a new high conductivity nuclear fuel form. Uranium dioxid...
The current US fleet of LWR’s are approaching the end of their original 40 year licenses. Most of th...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, February 2005.In...
H2O time-histories were studied within the H2/O2 system using a tunable diode laser system and a pre...
abstract: A distributed-parameter model is developed for a pressurized water reactor (PWR) in order ...
This project is developing a fundamental conceptual design for a gas-cooled, modular, pebble bed rea...
A computational study will be initiated during fiscal year 2006 to examine the feasibility of conver...
The sodium fast reactor is a type of liquid metal fast breeder nuclear reactor. Fast reactors offer ...
There is a need for a technique that is able to quickly and accurately quantify the amount of ^239Pu...
Uranium carbide (UC) has long been considered a potential alternative to uranium dioxide (UO2) fuel,...
Carbon monoxide (CO) is a toxic byproduct of incomplete combustion in hydrocarbon-fueled systems whi...
After the nuclear accident at Fukushima-Daiichi in 2011, a search for alternatives to a current fuel...
Pool boiling is an effective method used in many technical applications for a long time. Its highly ...
The threshold-fission (fertile) nature of Am-241 is used to destroy this minor actinide by capitaliz...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2010...
The objective of this work was to evaluate a new high conductivity nuclear fuel form. Uranium dioxid...
The current US fleet of LWR’s are approaching the end of their original 40 year licenses. Most of th...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, February 2005.In...
H2O time-histories were studied within the H2/O2 system using a tunable diode laser system and a pre...
abstract: A distributed-parameter model is developed for a pressurized water reactor (PWR) in order ...
This project is developing a fundamental conceptual design for a gas-cooled, modular, pebble bed rea...
A computational study will be initiated during fiscal year 2006 to examine the feasibility of conver...
The sodium fast reactor is a type of liquid metal fast breeder nuclear reactor. Fast reactors offer ...
There is a need for a technique that is able to quickly and accurately quantify the amount of ^239Pu...
Uranium carbide (UC) has long been considered a potential alternative to uranium dioxide (UO2) fuel,...
Carbon monoxide (CO) is a toxic byproduct of incomplete combustion in hydrocarbon-fueled systems whi...
After the nuclear accident at Fukushima-Daiichi in 2011, a search for alternatives to a current fuel...
Pool boiling is an effective method used in many technical applications for a long time. Its highly ...
The threshold-fission (fertile) nature of Am-241 is used to destroy this minor actinide by capitaliz...
Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2010...