Computational Methods for Sensitivity and Uncertainty Analysis in Criticality Safety [electronic resource].

Published:: Washington, D.C. : United States. Dept. of Energy, 1999.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Physical Description:: 9 Pages : digital, PDF file
Additional Creators:: Oak Ridge National Laboratory, United States. Department of Energy, and United States. Department of Energy. Office of Scientific and Technical Information

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Summary:

Interest in the sensitivity methods that were developed and widely used in the 1970s (the FORSS methodology at ORNL among others) has increased recently as a result of potential use in the area of criticality safety data validation procedures to define computational bias, uncertainties and area(s) of applicability. Functional forms of the resulting sensitivity coefficients can be used as formal parameters in the determination of applicability of benchmark experiments to their corresponding industrial application areas. In order for these techniques to be generally useful to the criticality safety practitioner, the procedures governing their use had to be updated and simplified. This paper will describe the resulting sensitivity analysis tools that have been generated for potential use by the criticality safety community.

Report Numbers:

E 1.99:ornl/cp-103192
ornl/cp-103192

Subject(s):

Nuclear Reactor Technology

Other Subject(s):

Note:

Published through SciTech Connect.
09/20/1999.
"ornl/cp-103192"
"41 W6 47 9W 1"
"DE00007408"
6th International Conference on Nuclear Criticality Safety, ICNC'99, Palais des Congres, Versailles, France, September 20-24, 1999.
Childs, R.L.; Broadhead, B.L.; Rearden, B.T.

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