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Abstract

This paper presents a technique for uncertainty analysis in the domain of nuclear and industrial safety, where the source of data are computer simulation programs. Such an universe of information can be viewed as an observable experiment space. In fact, in accident consequence studies, only a particular configuration of the simulation program is of interest. Therefore the accident consequence can be described as the effect of only some variables, i.e. the accident variables, whilst the rest of variables involved in the management of the program can be considered as background "latent' variables. This representation enables the analyst to observe the space of the accident variables as an ordinary experiment space in the "natural world". An application is given, which shows the practicality of Response Surface Methodology (RSM) as a tool for sensitivity and uncertainty analysis in nuclear reactor safety.

Additional information

Authors: OLIVI L JRC ISPRA ESTAB. (ITALY), JRC ISPRA ESTAB. (ITALY)
Bibliographic Reference: WORKSHOP ON METHODS OF ASSESSING THE OFF-SITE RADIOLOGICAL CONSEQUENCES OF NUCLEAR ACCIDENTS, LUXEMBOURG (GRAND-DUCHY OF LUXEMBOURG), APRIL 15-19, 1985 WRITE TO CEC LUXEMBOURG, DG XIII/A2, POB 1907 MENTIONING PAPER E 32052 ORA
Availability: Can be ordered online
Record Number: 1989123067500 / Last updated on: 1987-01-01
Category: PUBLICATION
Available languages: en