Maximum Individual Risks from Transported Spent Nuclear Fuel

by Ruth F. Weiner, Western Washington Univ, Bellingham, United States,
Sieglinde Neuhauser, Western Washington Univ, Bellingham, United States,
Frances L. Kanipe, Western Washington Univ, Bellingham, United States,



Document Type: Proceeding Paper

Part of: High Level Radioactive Waste Management 1993

Abstract: The computer code TICLD (Transportation Individual Center Line Dose) is used with the computer code RADTRAN 4 to calculate maximum individual dose and risk from transportation accidents in which radioactive material is released. Results of TICLD calculations are compared with closed-form calculations from RADTRAN 4 to assure consistency between the two codes. Calculation of individual doses at particular distances downwind from the postulated accident, for the six Pasquill stability classes, are also presented. Sensitivity analyses are also performed.

Subject Headings: Sensitivity analysis | Standards and codes | Risk management | Hazardous materials | Fuels | Computer programming | Accidents

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