RADTRAN 4: User guide. Volume 3

Neuhauser, K.S.; Kanipe, F.L.

doi:10.2172/10138044

Cited by 24 publications

(33 citation statements)

References 0 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…The RADTRAN 4 computer code (Neuhauser and Kanipe 1992) was used to calculate the routine (or incidentfree) radiological doses and accident risks of the in-transit segments between LLW generator sites and NTS. The HIGHWAY (Johnson et al 1993a) and INTERLINE (Johnson et al 1993b) computer codes were implemented to develop the routing data (e.g., shipping distances and population distributions along the routes) that is used by the RADTRAN 4 code.…”

Section: Methodology Descriptionmentioning

confidence: 99%

Life-Cycle Cost and Risk Analysis of Alternative Configurations for Shipping Low-Level Radioactive Waste to the Nevada Test Site

Daling¹,

Ross²,

Biwer³

1999

View full text Add to dashboard Cite

Section: Methodology Descriptionmentioning

confidence: 99%

Life-Cycle Cost and Risk Analysis of Alternative Configurations for Shipping Low-Level Radioactive Waste to the Nevada Test Site

Daling¹,

Ross²,

Biwer³

1999

View full text Add to dashboard Cite

“…The population density data for shipments on the Hanford Site were developed using site maps and suburban population densities to represent occupied facilities and rural population densities for all other areas adjacent to the transport route. (Neuhauser and Kanipe 1992) were used to calculate the transportation impacts, and the GEM1 software package ) was used to estimate the consequences to the maximum individuals.…”

Section: Dll Transportation Route Informationmentioning

confidence: 99%

“…The nonradiological impacts were calculated by multiplying the unit risk factors by the total shipping distances for all of the shipments in each shipping option. Nonradiological unit risk factors for incident-free transport were taken from Neuhauser and Kanipe (1992).…”

Section: D-4mentioning

confidence: 99%

“…The RADTRAN 4 computer code is organized into the following seven models (Neuhauser and Kanipe 1992 The code uses the first three models to calculate the potential population dose from normal, incident-free transportation and the first six models to calculate the risk to the population from user-defined accident scenarios. The economic model is not used in this study.…”

Section: D-6mentioning

confidence: 99%

“…Radiological accident impacts to the collective population (public) were calculated using the RADTRAN 4 computer code (Neuhauser and Kanipe 1992). The radiological impacts to the maximum onsite and offsite individuals, were calculated using GEM1 ).…”

Section: D-12mentioning

confidence: 99%

See 2 more Smart Citations

Lead test assembly irradiation and analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington

Safety¹

1997

View full text Add to dashboard Cite

Untitled

Mills¹,

Neuhauser²

1999

Risk Analysis

View full text Add to dashboard Cite

Calculation of accident dose-risk estimates with the RADTRAN code requires input data describing the population likely to be affected by the plume of radioactive material (RAM) released in a hypothetical transportation accident. In the existing model, population densities within 1/2 mile (0.8 km) of the route centerline are tabulated in three ranges (Rural, Suburban, and Urban). These population densities may be of questionable validity since the plume in the RADTRAN analysis is assumed to extend out to 120 km from the hypothetical accident site. We present a GIS-based population model which accounts for the actual distribution of population under a potential plume, and compare accident-risk estimates based on the resulting population densities with those based on the existing model. Results for individual points along a route differ greatly, but the cumulative accident risks for a sample route of a few hundred kilometers are found to be comparable, if not identical. We conclude, therefore, that for estimation of aggregate accident risks over typical routes of several hundred kilometers, the existing, simpler RADTRAN model is sufficiently detailed and accurate.

show abstract

RADTRAN 4: User guide. Volume 3

Cited by 24 publications

References 0 publications

Life-Cycle Cost and Risk Analysis of Alternative Configurations for Shipping Low-Level Radioactive Waste to the Nevada Test Site

Life-Cycle Cost and Risk Analysis of Alternative Configurations for Shipping Low-Level Radioactive Waste to the Nevada Test Site

Lead test assembly irradiation and analysis Watts Bar Nuclear Plant, Tennessee and Hanford Site, Richland, Washington

Untitled

Contact Info

Product

Resources

About