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ORIGEN2 calculations supporting TRIGA irradiated fuel data package

Description: ORIGEN2 calculations were performed for TRIGA spent fuel elements from the Hanford Neutron Radiography Facility. The calculations support storage and disposal and results include mass, activity,and decay heat. Comparisons with underwater dose-rate measurements were used to confirm and adjust the calculations.
Date: September 20, 1996
Creator: Schmittroth, F.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Weapons-Grade MOX Fuel Burnup Characteristics in Advanced Test Reactor Irradiation

Description: Mixed oxide (MOX) test capsules prepared with weapons-derived plutonium have been irradiated to a burnup of 50 GWd/t. The MOX fuel was fabricated at Los Alamos National Laboratory (LANL) by a master-mix process and has been irradiated in the Advanced Test Reactor (ATR) at the Idaho National Laboratory (INL). Previous withdrawals of the same fuel have occurred at 9, 21, 30, 40, and 50 GWd/t. Oak Ridge National Laboratory (ORNL) manages this test series for the Department of Energy’s Fissile Mate… more
Date: July 1, 2006
Creator: Chang, G. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Verify Super Double-Heterogeneous Spherical Lattice Model for Equilibrium Fuel Cycle Analysis AND HTR Spherical Super Lattice Model for Equilibrium Fuel Cycle Analysis

Description: The currently being developed advanced High Temperature gas-cooled Reactors (HTR) is able to achieve a simplification of safety through reliance on innovative features and passive systems. One of the innovative features in these HTRs is reliance on ceramic-coated fuel particles to retain the fission products even under extreme accident conditions. Traditionally, the effect of the random fuel kernel distribution in the fuel pebble / block is addressed through the use of the Dancoff correction fa… more
Date: November 1, 2005
Creator: Chang, Gray S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

VHTR Prismatic Super Lattice Model for Equilibrium Fuel Cycle Analysis

Description: The advanced Very High Temperature gas-cooled Reactor (VHTR), which is currently being developed, achieves simplification of safety through reliance on innovative features and passive systems. One of the VHTRs innovative features is the reliance on ceramic-coated fuel particles to retain the fission products under extreme accident conditions. The effect of the random fuel kernel distribution in the fuel prismatic block is addressed through the use of the Dancoff correction factor in the resonan… more
Date: September 1, 2006
Creator: Chang, G. S.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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