Published 2004 | Version v1
Book

Uncertainty and sensitivity analysis applied to coupled code calculations for a VVER plant transient

  • 1. Gesellschaft fuer Anlagen- und Reaktorsicherheit GRS mbH, ForschungsInst., 85748 Garching (Germany)

Description

The development of coupled codes, combining thermal-hydraulic system codes and 3D neutron kinetics, is an important step to perform best-estimate plant transient calculations. It is generally agreed that the application of best-estimate methods should be supplemented by an uncertainty and sensitivity analysis to quantify the uncertainty of the results. The paper presents results from the application of the GRS uncertainty and sensitivity method for a VVER-440 plant transient, which was already studied earlier for the validation of coupled codes. For this application, the main steps of the uncertainty method are described. Typical results of the method applied to the analysis of the plant transient by several working groups using different coupled codes are presented and discussed The results demonstrate the capability of an uncertainty and sensitivity analysis. (authors)

Additional details

Publishing Information

Publisher
American Nuclear Society - ANS
Imprint Place
La Grange Park (United States)
ISBN
0-89448683-7
Imprint Pagination
9 p.

Conference

Title
The Physics of Fuel Cycles and Advanced Nuclear Systems - Global Developments
Acronym
PHYSOR 2004
Dates
25-29 Apr 2004
Place
Chicago, IL (United States)

Optional Information

Notes
10 refs.