This report describes the design, fabrication, irradiation, and evaluation of two capsule tests containing U{sub 3}Si{sub 2} fuel particles in contact with aluminum. The tests were in support of fuel qualification for the Advanced Neutron Source (ANS) reactor, a high-powered research reactor that was planned for the Oak Ridge National Laboratory. At the time of these tests, the fuel consisted of U{sub 3}Si{sub 2}, containing highly enriched uranium dispersed in aluminum at a volume fraction of {approximately}0.15. The extremely high thermal flux in the target region of the High Flux Isotope Reactor provided up to 90% burnup in one 23-d cycle. Temperatures up to 450{degrees}C were maintained by gamma heating. Passive SiC temperature monitors...
Irradiation experiment HRB-21 is the first in a series of test capsules that are designed to provide...
Irradiations of test fuel specimens and experimental fue elements are conducted both in capsules and...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...
A high-density fuel based on U/sub 3/Si/sub 2/ dispersed in aluminum has been developed and tested f...
This report describes the development and qualification plan for the fuel for the Advanced Neutron S...
Activities in a project aimed at the improvement of fuel elements for high flux test reactors are re...
Six high-density, low-enriched U/sub 3/Si/sub 2/-Al dispersion fuel elements have been tested in the...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...
Development and irradiation testing of high-density fuels have been conducted by the US RERTR Progra...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...
Abstract – The AGR-1 irradiation experiment contains seventy-two individual cylindrical fuel compact...
The irradiation performance of U3Si dispersion fuel in an Al matrix, U3Si-Al, under the Hi-Flux Adva...
Few data exist for UO{sub 2} or UN within the notional design space for the Prometheus-1 reactor (lo...
This report presents the fuel fabrication development for the Advanced Neutron Source (ANS) reactor....
Irradiation experiment HRB-21 is the first in a series of test capsules that are designed to provide...
Irradiations of test fuel specimens and experimental fue elements are conducted both in capsules and...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...
A high-density fuel based on U/sub 3/Si/sub 2/ dispersed in aluminum has been developed and tested f...
This report describes the development and qualification plan for the fuel for the Advanced Neutron S...
Activities in a project aimed at the improvement of fuel elements for high flux test reactors are re...
Six high-density, low-enriched U/sub 3/Si/sub 2/-Al dispersion fuel elements have been tested in the...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...
Development and irradiation testing of high-density fuels have been conducted by the US RERTR Progra...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...
Abstract – The AGR-1 irradiation experiment contains seventy-two individual cylindrical fuel compact...
The irradiation performance of U3Si dispersion fuel in an Al matrix, U3Si-Al, under the Hi-Flux Adva...
Few data exist for UO{sub 2} or UN within the notional design space for the Prometheus-1 reactor (lo...
This report presents the fuel fabrication development for the Advanced Neutron Source (ANS) reactor....
Irradiation experiment HRB-21 is the first in a series of test capsules that are designed to provide...
Irradiations of test fuel specimens and experimental fue elements are conducted both in capsules and...
The central aspect of the safety philosophy for a small HTR is the retention of fission products, pa...