The MARIA reactor is a high-flux multipurpose research reactor which is water-cooled and moderated with both beryllium and water. Standard HEU (80% {sup 235}U)fuel assemblies consist of six concentric fuel tubes of a U-Al alloy clad in aluminum. Although the inventory of HEU (80%) fuel is nearly exhausted, a supply of highly-loaded 36%-enriched fuel assemblies is available at the reactor site. Neutronic equilibrium studies have been made to determine the relative performance of fuels with enrichments of 80%, 36% and 19.7%. These studies indicate that LEU (19.7%) densities of about 2.5 gU/cm{sup 3} and 3.8 gU/cm{sup 3} are required to match the performance of the MARIA reactor with 80%-enriched and with 36%-enriched fuels, respectively
A plan is being developed for the conversion of the NIST research reactor (NBSR) from high-enriched ...
Comparative studies for conversion of the fuel from HEU to LEU in the miniature neutron source react...
Reactor kinetic parameters, reactivity feedback coefficients, and control rod reactivity worths have...
A neutronic feasibility study was performed to determine the uranium densities that would be require...
The WWR-SM research reactor in Uzbekistan has operated at 10 MW since 1979, using Russian-supplied I...
The MARIA reactor at the Institute of Atomic Energy (IAE) in Swierk (30 km SE of Warsaw) in the Repu...
A computational study has been initiated at ORNL to examine the feasibility of converting the High F...
Equilibrium fuel cycle comparisons for the IR-8 research reactor were made for HEU(90%), HEU(36%), a...
The Massachusetts Institute of Technology (MIT) reactor (MITR-II), based in Cambridge, Massachusetts...
A neutronic feasibility study for converting the High Flux Beam Reactor at Brookhaven National Labor...
The Advanced Test Reactor (ATR) is a high power density, high neutron flux research reactor operatin...
Feasibility studies have been performed to convert both the Brookhaven Medical Research Reactor (BMR...
An initial safety study for potential LEU conversion of the Budapest Research Reactor was completed....
Design and safety analyses to determine an optimum LEU fuel assembly design using U{sub 3}Si{sub 2}-...
International concerns about the proliferation of nuclear materials have generated interest in the d...
A plan is being developed for the conversion of the NIST research reactor (NBSR) from high-enriched ...
Comparative studies for conversion of the fuel from HEU to LEU in the miniature neutron source react...
Reactor kinetic parameters, reactivity feedback coefficients, and control rod reactivity worths have...
A neutronic feasibility study was performed to determine the uranium densities that would be require...
The WWR-SM research reactor in Uzbekistan has operated at 10 MW since 1979, using Russian-supplied I...
The MARIA reactor at the Institute of Atomic Energy (IAE) in Swierk (30 km SE of Warsaw) in the Repu...
A computational study has been initiated at ORNL to examine the feasibility of converting the High F...
Equilibrium fuel cycle comparisons for the IR-8 research reactor were made for HEU(90%), HEU(36%), a...
The Massachusetts Institute of Technology (MIT) reactor (MITR-II), based in Cambridge, Massachusetts...
A neutronic feasibility study for converting the High Flux Beam Reactor at Brookhaven National Labor...
The Advanced Test Reactor (ATR) is a high power density, high neutron flux research reactor operatin...
Feasibility studies have been performed to convert both the Brookhaven Medical Research Reactor (BMR...
An initial safety study for potential LEU conversion of the Budapest Research Reactor was completed....
Design and safety analyses to determine an optimum LEU fuel assembly design using U{sub 3}Si{sub 2}-...
International concerns about the proliferation of nuclear materials have generated interest in the d...
A plan is being developed for the conversion of the NIST research reactor (NBSR) from high-enriched ...
Comparative studies for conversion of the fuel from HEU to LEU in the miniature neutron source react...
Reactor kinetic parameters, reactivity feedback coefficients, and control rod reactivity worths have...