For several years, the US Nuclear Regulatory Commission has sponsored the development of methods for improving capabilities to analyze the effects of postulated accidents in nuclear facilities; the accidents of interest are those that could occur during nuclear materials handling. At the Los Alamos National Laboratory, this program has resulted in three computer codes: FIRAC, EXPAC, and TORAC. These codes are designed to predict the effects of fires, explosions, and tornadoes in nuclear facilities. Particular emphasis is placed on the movement of airborne radioactive material through the gaseous effluent treatment system of a nuclear installation. The design, construction, and calibration of an experimental ventilation system to verify the ...
When a hazardous aerosol or gas is inadvertently or deliberately released in an occupied facility, t...
A computational fluid dynamics (CFD) based fire model has been successfully coupled to standard fini...
Analyses of severe accidents in nuclear power plants by using integral codes are necessary in order ...
The FIRAC computer code predicts fire-induced transients in nuclear fuel cycle facility ventilation ...
This paper describes a multilaboratory research program that is directed toward addressing many ques...
Previous studies of the safety and environmental (S and E) aspects of the HYLIFE-II inertial fusion ...
ECART can simulate the thermal-hydraulic behavior of LWR and GCR plants under severe accident condit...
ECART can simulate the thermal-hydraulic behavior of LWR and GCR plants under severe accident condit...
Abstract Previous studies of the safety and environmental (S&E) aspects of the HYLIFE-II inertia...
International audienceThe outbreak of fires in nuclear power plants is a major risk due to the poten...
Full-scale fire experiments were carried out in a laboratory designed according to the standard EN54...
Full-scale fire experiments were carried out in a laboratory designed according to the standard EN54...
This work concerns with the consequences analysis of vapour cloud explosion (VCE) on the nuclear rea...
A fire in a nuclear power plant (NPP) can damage equipment needed to safely operate the plant and th...
Right after the events unfolded in Fukushima Daiichi, the European Union countries agreed in subject...
When a hazardous aerosol or gas is inadvertently or deliberately released in an occupied facility, t...
A computational fluid dynamics (CFD) based fire model has been successfully coupled to standard fini...
Analyses of severe accidents in nuclear power plants by using integral codes are necessary in order ...
The FIRAC computer code predicts fire-induced transients in nuclear fuel cycle facility ventilation ...
This paper describes a multilaboratory research program that is directed toward addressing many ques...
Previous studies of the safety and environmental (S and E) aspects of the HYLIFE-II inertial fusion ...
ECART can simulate the thermal-hydraulic behavior of LWR and GCR plants under severe accident condit...
ECART can simulate the thermal-hydraulic behavior of LWR and GCR plants under severe accident condit...
Abstract Previous studies of the safety and environmental (S&E) aspects of the HYLIFE-II inertia...
International audienceThe outbreak of fires in nuclear power plants is a major risk due to the poten...
Full-scale fire experiments were carried out in a laboratory designed according to the standard EN54...
Full-scale fire experiments were carried out in a laboratory designed according to the standard EN54...
This work concerns with the consequences analysis of vapour cloud explosion (VCE) on the nuclear rea...
A fire in a nuclear power plant (NPP) can damage equipment needed to safely operate the plant and th...
Right after the events unfolded in Fukushima Daiichi, the European Union countries agreed in subject...
When a hazardous aerosol or gas is inadvertently or deliberately released in an occupied facility, t...
A computational fluid dynamics (CFD) based fire model has been successfully coupled to standard fini...
Analyses of severe accidents in nuclear power plants by using integral codes are necessary in order ...