Uncertainty and Sensitivity Analysis of Severe Accidents Simulations at VVER in the Framework of the IAEA CRP I31033
Description
The International Atomic Energy Agency (IAEA) launched in 2019 the Cooperative Research Project (CRP) I31033 entitled "Advancing the State-of-Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water-Cooled Reactors". The main goal is to advance the understanding and characterization of sources of uncertainty and investigate their effects on the key figure-of-merits (FOMs) of the severe accident codes predictions in water cooled reactors (WCRs). Having this in mind, within the five-year duration of the CRP, 22 organizations representing 18 Member States have been developing and evaluating calculation platforms based on the currently available severe accident codes and relevant uncertainty tools for uncertainty and sensitivity (U&S) analyses of severe accident scenarios in different WCRs, i.e. PWR, BWR, CANDU, VVER, and SMR. In the CRP framework, the U&S analysis of the QUENCH-06 experiment has also been performed to give relevant insights.
Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs. Book of Abstracts
- Imprint Pagination
- 146 p.
- Journal Page Range
- p. 106-107
- Report number
- IAEA-CN--308
Conference
- Title
- Strengthening Safety of Evolutionary and Innovative Reactor Designs
- Acronym
- International Conference on Topical Issues in Nuclear Installation Safety
- Dates
- 18-21 Oct 2022
- Place
- Vienna (Austria)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54004941
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BWR TYPE REACTORS; CANDU TYPE REACTORS; NUCLEAR ENERGY; REACTOR ACCIDENT SIMULATION; SENSITIVITY ANALYSIS; SEVERE ACCIDENTS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; ENERGY; ENRICHED URANIUM REACTORS; HEAVY WATER MODERATED REACTORS; POWER REACTORS; PRESSURE TUBE REACTORS; PWR TYPE REACTORS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 3 refs.
- Secondary number(s)
- IAEA-CN--308-146