Application of the ASTECv2.1.1.6 severe accident computer code and SUNSET tool for; uncertainty and sensitivity analyses on MCCI VVER1000 test case
- 1. Institute for Nuclear Research and Nuclear Energy, Bulgarian Academy of Sciences, Sofia (Bulgaria)
Description
This article concerns an uncertainty and sensitivity investigation of certain parameters in the molten corium concrete interaction (MCCI) test case for VVER1000. It has been used the MEDICIS/ASTECv2.1.1.6 severe accident computer code to describe the basic parameters behaviour and the main phenomena arising during the MCCI in VVER1000 reactor design. The uncertainties in some parameters in the deterministic calculations requires additional investigations. An opportunity for an uncertainty and sensitivity analyses gives SUNSET computational tool which is a part of ASTEC computer code. In this article it have been investigated an influence of eight input parameters on two basic output parameters. It was found out to what extent each one of the eight input parameters affect on the studied output parameters. There also have been collected two groups of input parameters determining the maximal and minimal ranges of the output parameters uncertainties. Keywords: Molten Corium Concrete Interaction, Severe accident, VVER-1000, ASTEC v2.1.1.6 computer code, SUNSET tool. (author)
Availability note (English)
Available from: https://bgns-transactions.org/journals/volume-25/Additional details
Identifiers
Publishing Information
- Journal Title
- BgNS Transactions
- Journal Volume
- 25
- Journal Issue
- 1
- Journal Page Range
- p. 27-32
- ISSN
- 1310-8727
INIS
- Country of Publication
- Bulgaria
- Country of Input or Organization
- Bulgaria
- INIS RN
- 54010312
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; CORIUM; MOLTEN CORE-CONCRETE INTERACTIONS; REACTOR ACCIDENTS; REACTOR DESIGN; SENSITIVITY ANALYSIS; SEVERE ACCIDENTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; DESIGN; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR LIFE CYCLE; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 5 tabs., 6 figs., 14 refs.