Feasibility studies have been performed to convert both the Brookhaven Medical Research Reactor (BMRR) and the High Flux Beam Reactor (HFBR) at the Brookhaven National Laboratory from the use of HEU (93%) fuel to the use of LEU (<20%) fuel. The studies are intended to determine suitable LEU fuels that will provide fuel lifetime and neutron flux performance similar to the current HEU fuels. Both reactors use MTR-type fuel assemblies: the BMRR has 18 fuel plates with 140g {sup 235}U (0.43 gU/cm{sup 3}) and the HFBR has 20 plates, of which 18 are fuel with 351 g {sup 235}U (1.1 gU/cm{sup 3})
A study has been carried out to understand how the NIST research reactor (NBSR) might be converted f...
Engineering design studies are underway to assess the feasibility of converting the High Flux Isotop...
Equilibrium fuel cycle comparisons for the IR-8 research reactor were made for HEU(90%), HEU(36%), a...
A neutronic feasibility study for converting the High Flux Beam Reactor at Brookhaven National Labor...
A neutronic feasibility study was performed to determine the uranium densities that would be require...
A computational study has been initiated at ORNL to examine the feasibility of converting the High F...
Design and safety analyses to determine an optimum LEU fuel assembly design using U{sub 3}Si{sub 2}-...
In order to consider the conversion of the High Flux Isotope Reactor (HFIR) from highly enriched ura...
The Advanced Test Reactor (ATR) is a high power density, high neutron flux research reactor operatin...
This report documents progress made during FY 2010 in studies of converting the High Flux Isotope Re...
This report documents progress made during FY 2008 in studies of converting the High Flux Isotope Re...
At the request of the Department of Energy, the RERTR Program has summarized the conversion status o...
The Advanced Test Reactor (ATR) is a high power density and high neutron flux research reactor opera...
The MARIA reactor is a high-flux multipurpose research reactor which is water-cooled and moderated w...
Engineering design studies are underway to assess the feasibility of converting the High Flux Isotop...
A study has been carried out to understand how the NIST research reactor (NBSR) might be converted f...
Engineering design studies are underway to assess the feasibility of converting the High Flux Isotop...
Equilibrium fuel cycle comparisons for the IR-8 research reactor were made for HEU(90%), HEU(36%), a...
A neutronic feasibility study for converting the High Flux Beam Reactor at Brookhaven National Labor...
A neutronic feasibility study was performed to determine the uranium densities that would be require...
A computational study has been initiated at ORNL to examine the feasibility of converting the High F...
Design and safety analyses to determine an optimum LEU fuel assembly design using U{sub 3}Si{sub 2}-...
In order to consider the conversion of the High Flux Isotope Reactor (HFIR) from highly enriched ura...
The Advanced Test Reactor (ATR) is a high power density, high neutron flux research reactor operatin...
This report documents progress made during FY 2010 in studies of converting the High Flux Isotope Re...
This report documents progress made during FY 2008 in studies of converting the High Flux Isotope Re...
At the request of the Department of Energy, the RERTR Program has summarized the conversion status o...
The Advanced Test Reactor (ATR) is a high power density and high neutron flux research reactor opera...
The MARIA reactor is a high-flux multipurpose research reactor which is water-cooled and moderated w...
Engineering design studies are underway to assess the feasibility of converting the High Flux Isotop...
A study has been carried out to understand how the NIST research reactor (NBSR) might be converted f...
Engineering design studies are underway to assess the feasibility of converting the High Flux Isotop...
Equilibrium fuel cycle comparisons for the IR-8 research reactor were made for HEU(90%), HEU(36%), a...