Review of models applicable to accident aerosols

doi:10.2172/6055592

Abstract

Estimations of potential airborne-particle releases are essential in safety assessments of nuclear-fuel facilities. This report is a review of aerosol behavior models that have potential applications for predicting aerosol characteristics in compartments containing accident-generated aerosol sources. Such characterization of the accident-generated aerosols is a necessary step toward estimating their eventual release in any accident scenario. Existing aerosol models can predict the size distribution, concentration, and composition of aerosols as they are acted on by ventilation, diffusion, gravity, coagulation, and other phenomena. Models developed in the fields of fluid mechanics, indoor air pollution, and nuclear-reactor accidents are reviewed with this nuclear fuel facility application in mind. The various capabilities of modeling aerosol behavior are tabulated and discussed, and recommendations are made for applying the models to problems of differing complexity.

Review of the chronic exposure pathways models in MACCS (MELCOR Accident Consequence Code System) and several other well-known probabilistic risk assessment models

Tveten, U. June 1990

The purpose of this report is to document the results of the work performed by the author in connection with the following task, performed for US Nuclear Regulatory Commission, (USNRC) Office of Nuclear Regulatory Research, Division of Systems Research: MACCS Chronic Exposure Pathway Models: Review the chronic exposure pathway models implemented in the MELCOR Accident Consequence Code System (MACCS) and compare those models to the chronic exposure pathway models implemented in similar codes developed in countries that are members of the OECD. The chronic exposures concerned are via: the terrestrial food pathways, the water pathways, the long-term groundshine pathway, andmore »« less
DOI: 10.2172/7101613

Full Text Available
BULGEX: a computer code to determine the deformation and the onset of bulging of Zircaloy fuel rod cladding (applicable for loss of coolant accident conditions)

Merckx, K.R. December 1974
BULGEX: a computer code to determine the deformation and the onset of bulging of Zircaloy fuel rod cladding (applicable for loss of coolant accident conditions)

Merckx, K.R. January 1975
BULGEX: a computer code to determine the deformation and the onset of bulging of Zircaloy fuel rod cladding (applicable for loss of coolant accident conditions)

Merckx, K.R. December 1974

A deformational model for zircaloy-cladding under the temperature, stress, and environmental conditions encountered during a LOCA has been incorporated in a time incremental code, BULGEX, which determines the deformation history, internal pressure history, and the onset of clad bulging. The theoretical bases for the BULGEX code, methods for interpreting these data, the resultant plastic and creep deformation model and stability criterion, and the results of sensitivity studies on typical BWR geometries are presented. (auth)
INTERIM SUMMARY OF WORK APPLICABLE TO ECC ON PHYSICO-CHEMICAL STUDIES OF CLAD UO$sub 2$ UNDER REACTOR ACCIDENT CONDITIONS.

White, J.F. January 1968

Title: Review of models applicable to accident aerosols

Abstract

Citation Formats

Review of the chronic exposure pathways models in MACCS (MELCOR Accident Consequence Code System) and several other well-known probabilistic risk assessment models

BULGEX: a computer code to determine the deformation and the onset of bulging of Zircaloy fuel rod cladding (applicable for loss of coolant accident conditions)

BULGEX: a computer code to determine the deformation and the onset of bulging of Zircaloy fuel rod cladding (applicable for loss of coolant accident conditions)

BULGEX: a computer code to determine the deformation and the onset of bulging of Zircaloy fuel rod cladding (applicable for loss of coolant accident conditions)

INTERIM SUMMARY OF WORK APPLICABLE TO ECC ON PHYSICO-CHEMICAL STUDIES OF CLAD UO$sub 2$ UNDER REACTOR ACCIDENT CONDITIONS.