An experiment containing WG-MOX fuel has been designed and irradiated from 1998 to 2004 in the Advanced Test Reactor (ATR) at the Idaho National Engineering and Environmental Laboratory (INEEL). Important neutronics parameters were computed using novel Monte Carlo methods. The purpose of this summary is to compare the Weapons-Grade Mixed Oxide fuel (WG-MOX) Zr-tube’s neutron spectrum in ATR and PWR. The results indicate that the Zrtube’s neutron spectrum in ATR are softer than in PWR
The United States (US) Department of Energy Fissile Materials Disposition Program (FMDP) began studi...
The most attractive way to dispose of weapons-grade plutonium (WGPu) is to use it as fuel in existin...
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Cent...
This paper presents a new method for calculating the burnup of nuclear reactor fuel, the MCWO-MS met...
Mixed oxide (MOX) test capsules prepared with weapons-derived plutonium have been irradiated to a bu...
This report using the detailed ATR quarter core model calculated neutronic tallies, the MCWO-calcula...
The treatment of spent fuel produced in nuclear power generation is one of the most important issues...
Simulations and experiments have been carried out to investigate the neutron emission characteristic...
The US (US) Department of Energy Fissile Materials Disposition Program has begun studies for disposa...
The Department of Energy (DOE) Fissile Disposition Program (FMDP) has announced that reactor irradia...
Numerous technical issues must be resolved before LWR operating licenses can be amended to allow the...
This report documents the MCWO-calculated Zr-cladding fast neutron fluence (E > 0.1 MeV and E > 1.0 ...
Contract DE-AC07-99ID13727 This report documents the MCWO-calculated Zr-cladding fast neutron fluenc...
An intense worldwide effort is now under way to find means of reducing the stockpile of weapons-grad...
The most effective method for transmuting long-lived isotopes contained in spent nuclear fuel into s...
The United States (US) Department of Energy Fissile Materials Disposition Program (FMDP) began studi...
The most attractive way to dispose of weapons-grade plutonium (WGPu) is to use it as fuel in existin...
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Cent...
This paper presents a new method for calculating the burnup of nuclear reactor fuel, the MCWO-MS met...
Mixed oxide (MOX) test capsules prepared with weapons-derived plutonium have been irradiated to a bu...
This report using the detailed ATR quarter core model calculated neutronic tallies, the MCWO-calcula...
The treatment of spent fuel produced in nuclear power generation is one of the most important issues...
Simulations and experiments have been carried out to investigate the neutron emission characteristic...
The US (US) Department of Energy Fissile Materials Disposition Program has begun studies for disposa...
The Department of Energy (DOE) Fissile Disposition Program (FMDP) has announced that reactor irradia...
Numerous technical issues must be resolved before LWR operating licenses can be amended to allow the...
This report documents the MCWO-calculated Zr-cladding fast neutron fluence (E > 0.1 MeV and E > 1.0 ...
Contract DE-AC07-99ID13727 This report documents the MCWO-calculated Zr-cladding fast neutron fluenc...
An intense worldwide effort is now under way to find means of reducing the stockpile of weapons-grad...
The most effective method for transmuting long-lived isotopes contained in spent nuclear fuel into s...
The United States (US) Department of Energy Fissile Materials Disposition Program (FMDP) began studi...
The most attractive way to dispose of weapons-grade plutonium (WGPu) is to use it as fuel in existin...
In 1967, a series of critical experiments were conducted at the Westinghouse Reactor Evaluation Cent...