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Title: Conversion of OPAL from U3Si2 to High Density U–Mo Fuel. Annex III
Authors: Braoudakis, G
Villarino, EA
Keywords: Absorption
Fuel consumption
Fuel plates
Highly enriched uranium
Neutron flux
OPAL Reactor
Reactivity coefficients
Reactor cores
Research reactors
Uranium silicides
Issue Date: Apr-2021
Publisher: International Atomic Energy Agency
Citation: Braoudakis, G., & Villarino, E. (2021). Conversion of OPAL from U3Si2 to High Density U–Mo Fuel Annex III. In International Atomic Energy Agency (IAEA), Impact of fuel density on performance and economy of research reactors. (pp. 44-53). Vienna : International Atomic Energy Agency. Retrieved from:
Series/Report no.: IAEA Nuclear Energy Series;NF-T-2.7
Abstract: The ongoing development of high density low enriched uranium (LEU) fuels to replace the current application of highly enriched uranium (HEU) fuels, in accordance with the non‑proliferation and security objectives of the Global Threat Reduction Initiative (GTRI), offers an opportunity to assess the impact of such fuels on performance and reactor core parameters. The performance of the current 4.8 gU/cm3 U3Si2 fuel in the Open Pool Australian Lightwater (OPAL) reactor is compared against that estimated for a variety of potential U–Mo high density fuels that range in density from 6.0 to 8.0 gU/cm3. The comparison includes cycle length, fuel usage, shutdown system performance, neutron fluxes in irradiation positions, kinetic parameters and reactivity feedback coefficients.High performance research reactors depend on a compact core design to maximize the neutron flux available for irradiation and beam facilities. The most readily available technology to achieve this goal is the use of HEU fuels. The extensive experience and demonstrable reliability and performance of such fuels makes them a clear choice for most of the high performance research reactors around the world. In addition, there are gains in fuel economy through maximization of fuel burnup and minimization of parasitic neutron absorption, which is present in some of the LEU fuels. In the spirit of GTRI, new high density LEU fuels are being developed with the intention of providing a non‑proliferation option while maintaining much of the performance expected from HEU fuels. One of the most promising high density LEU fuels is a uranium–molybdenum (U–Mo) alloy dispersion type fuel in an aluminium matrix. The addition of Mo stabilizes the uranium during irradiation and several different densities of uranium and alloy compositions are considered in this study, as no qualified fuel exists at this time.The current core design is optimized for the use of 4.8 gU/cm3 U3Si2 fuel. This study was performed while maintaining the core and fuel dimensions (specifically the fuel meat, fuel plate and coolant channel thicknesses) and only the fuel meat composition was modified. The estimated performance parameters were calculated using the same codes and methods that were used for the U3Si2 calculations. In this way a direct comparison can be made to assess the impact of using high density U–Mo fuel. © The Author
Gov't Doc #: 9982
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