Uncertainty analysis of preclosure accident doses for the Yucca Mountain repository

Uncertainty analysis of preclosure accident doses for the Yucca Mountain repository [electronic resource]

This study presents a generic methodology that can be used to evaluate the uncertainty in the calculated accidental offsite doses at the Yucca Mountain repository during the preclosure period. For demonstration purposes, this methodology is applied to two specific accident scenarios: the first invol...

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Bibliographic Details
Online Access: Online Access
Corporate Author: Sandia National Laboratories (Researcher)
Format: Government Document Electronic eBook
Language:English
Published: Albuquerque, N.M. : Oak Ridge, Tenn. : Sandia National Laboratories. ; distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1990.
Subjects:
Radiation Doses.
Mathematical Models.
Krypton 85.
Spent Fuels.
Air.
High-level Radioactive Wastes.
Risk Assessment.
Environmental Exposure.
Particle Size.
Yucca Mountain Project.
Radiation Accidents.
Underground Disposal.
Yucca Mountain.
Radionuclide Migration.
Nuclear Fuels.

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Call Number: E 1.99: conf-910435--40
E 1.99: conf-910435--40 Available

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