A thermally induced fuel-plate dispersion model was developed to analyze for dispersive potential and determine the onset of fuel plate dispersion for aluminum-based research and test reactor fuels. The effect of rapid energy deposition in a fuel plate was simulated. Several data types for aluminum-based fuels tested in the Nuclear Safety Research Reactor (NSRR) facility in Japan and in the Transient Reactor Test (TREAT) facility in Idaho, US, were reviewed. Analyses of experiments show that the onset of fuel dispersion is clearly linked to a sharp rise in the predicted strain rate, which further coincides with the onset of aluminum vaporization. Analysis also shows that aluminum oxidation and exothermal chemical reaction between the fuel a...
A high-energy Xe ion irradiation experiment was conducted to investigate the temperature dependence ...
Recent irradiation tests of U{sub 3}Si-Al dispersion fuel have shown performance limitations of this...
High-performance research reactors require fuel that operates at high specific power to high fission...
A thermally induced dispersion model was developed to analyze for dispersive potential and determine...
The Dispersion Analysis Research Tool (DART) contains models for fission-gas induced fuel swelling, ...
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 primary physical models that form the basis of the DART mechanistic comput...
The mechanical properties of two aluminum alloys and a fuel dispersion have been investigated for th...
Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium c...
The RERTR-3 irradiation test was designed to investigate the irradiation behavior of aluminum matrix...
The dispersion fuel concept offers a method for minimizing irradiation- induced property changes in ...
The planned reactor for the Advanced Neutron Source (ANS) will use closely spaced arrays of involute...
In order to advance understanding of the breakaway swelling behavior of U-Mo/Al dispersion fuel unde...
Development and irradiation testing of high-density fuels have been conducted by the US RERTR Progra...
Dispersion fuels represent a significant departure from typical ceramic fuels to address swelling an...
A high-energy Xe ion irradiation experiment was conducted to investigate the temperature dependence ...
Recent irradiation tests of U{sub 3}Si-Al dispersion fuel have shown performance limitations of this...
High-performance research reactors require fuel that operates at high specific power to high fission...
A thermally induced dispersion model was developed to analyze for dispersive potential and determine...
The Dispersion Analysis Research Tool (DART) contains models for fission-gas induced fuel swelling, ...
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 primary physical models that form the basis of the DART mechanistic comput...
The mechanical properties of two aluminum alloys and a fuel dispersion have been investigated for th...
Reported radioactivity in the Low-Intensity Test Reactor (LITR) water coolant traceable to uranium c...
The RERTR-3 irradiation test was designed to investigate the irradiation behavior of aluminum matrix...
The dispersion fuel concept offers a method for minimizing irradiation- induced property changes in ...
The planned reactor for the Advanced Neutron Source (ANS) will use closely spaced arrays of involute...
In order to advance understanding of the breakaway swelling behavior of U-Mo/Al dispersion fuel unde...
Development and irradiation testing of high-density fuels have been conducted by the US RERTR Progra...
Dispersion fuels represent a significant departure from typical ceramic fuels to address swelling an...
A high-energy Xe ion irradiation experiment was conducted to investigate the temperature dependence ...
Recent irradiation tests of U{sub 3}Si-Al dispersion fuel have shown performance limitations of this...
High-performance research reactors require fuel that operates at high specific power to high fission...