Published 2004 | Version v1
Miscellaneous

Quantification of the uncertainties of the physical models of CATHARE 2

  • 1. CEA-Grenoble, DEN/DER/SSTH, Grenoble (France)

Description

The goal of this paper is to draw up a balance sheet of the use of the CIRCE tool, by CEA (France) for the CATHARE 2 code. CIRCE is a statistical tool which is aimed at estimating the uncertainties of the physical models of CATHARE 2 and which can replace the expert judgment generally used. The determination of these uncertainties, with CIRCE or expert judgment, makes up an essential first step for the majority of methods in uncertainty analysis. In the first part of the paper, the CIRCE tool is rapidly described and attention is focused on a hypothesis of linearity made by CIRCE. A work program using CIRCE for the determination of the uncertainties of some physical models of CATHARE 2 has been defined and achieved, the studies of which are listed. Due to the hypothesis of linearity and also because CIRCE is a quite new statistical tool, some precautions must be taken when using it. They are precisely described in the second part of this paper and illustrated in an example. (author)

Part of:
BE-2004: International meeting on updates in best estimate methods in nuclear installation safety analysis. Proceedings

Additional details

Publishing Information

Imprint Title
BE-2004: International meeting on updates in best estimate methods in nuclear installation safety analysis. Proceedings
Imprint Pagination
376 p.
Journal Page Range
p. 111-117

Conference

Title
International meeting on updates in best estimate methods in nuclear installation safety analysis
Acronym
BE-2004
Dates
14-18 Nov 2004
Place
Washington, DC (United States)

INIS

Country of Publication
International Atomic Energy Agency (IAEA)
Country of Input or Organization
International Atomic Energy Agency (IAEA)
INIS RN
36058520
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
C CODES; LOSS OF COOLANT; MATHEMATICAL MODELS; RELIABILITY; RISK ASSESSMENT; STATISTICS
Descriptors DEC
ACCIDENTS; COMPUTER CODES; MATHEMATICS; REACTOR ACCIDENTS

Optional Information

Notes
6 refs, 6 figs, 2 tabs