Uncertainties in offsite consequence analysis [electronic resource]
Saved in:
| Online Access: |
Online Access (via OSTI) |
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| Corporate Author: | |
| Format: | Government Document Electronic eBook |
| Language: | English |
| Published: |
Washington, D.C. : Oak Ridge, Tenn. :
U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,
1996.
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| Abstract: | The development of two new probabilistic accident consequence codes, MACCS and COSYMA, was completed in 1990. These codes estimate the consequences from the accidental releases of radiological material from hypothesized accidents at nuclear installations. In 1991, the U.S. Nuclear Regulatory Commission and the European Commission began co-sponsoring 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 using a formal expert judgment elicitation and evaluation process. This paper focuses on the methods used in and results of this on-going joint effort. |
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| Item Description: | Published through SciTech Connect. 03/01/1996. "nureg/cp--0149-vol.2" " conf-9510156--vol.2" "TI96007985" 23. water reactor safety information meeting, Bethesda, MD (United States), 23-25 Oct 1995. Young, M.L.; Harper, F.T.; Lui, C.H. |
| Physical Description: | pp. 377-390 : digital, PDF file. |