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Probabilistic accident consequence uncertainty analysis -- Uncertainty assessment for internal dosimetry. Volume 1: Main report

By L.H.J. Goossens, B.C.P. Kraan, R.M. Cooke, J.D. Harrison, F.T. Harper and S.C. Hora

Abstract

The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequence from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the US Nuclear Regulatory Commission and the Commission of the European Communities began cosponsoring a joint uncertainty analysis of the two codes. The ultimate objective of this joint effort was to systematically develop credible and traceable uncertainty distributions for the respective code input variables. A formal expert judgment elicitation and evaluation process was identified as the best technology available for developing a library of uncertainty distributions for these consequence parameters. This report focuses on the results of the study to develop distribution for variables related to the MACCS and COSYMA internal dosimetry models

Topics: Probability, Numerical Data, International Cooperation, 99 Mathematics, Computers, Information Science, Management, Law, Miscellaneous, Dosimetry, Data Covariances, Reactor Accidents, 22 Nuclear Reactor Technology, C Codes, 56 Biology And Medicine, Applied Studies, Radiation Doses, Nuclear Power Plants, M Codes
Publisher: Univ. of Hawaii, Hilo, HI (United States)
Year: 1998
DOI identifier: 10.2172/291004
OAI identifier:
Provided by: UNT Digital Library
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