Uncertainty and sensitivity analysis applied to coupled code calculations for a VVER plant transient
Creators
- 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)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 42097595
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; REACTOR KINETICS EQUATIONS; SENSITIVITY ANALYSIS; THERMAL HYDRAULICS; THREE-DIMENSIONAL CALCULATIONS; VALIDATION; WWER TYPE REACTORS
- Descriptors DEC
- ENRICHED URANIUM REACTORS; EQUATIONS; FLUID MECHANICS; HYDRAULICS; MECHANICS; POWER REACTORS; PWR TYPE REACTORS; REACTORS; TESTING; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 10 refs.