Uncertainty and Sensitivity Analysis of Severe Accidents Simulations at VVER in the Framework of the IAEA CRP I31033
- 1. IBRAE RAN, Moscow, Russian Federation
- 2. NNEGC "ENERGOATOM", Kyiv, Ukraine
- 3. OKB "Gidropress" JSC, Podolsk, Russian Federation
Description
The 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). In the framework of the CRP four institutions NNEGC "ENERGOATOM", OKB "Gidropress" JSC, IBRAE RAN, and NRC "KURCHATOV INSTITUTE" preformed uncertainty and sensitivity analysis of VVER rectors. Two severe accident codes are used MELCOR 1.8.5 and SOCRAT together with in-house developed uncertainty tools. Each participant has selected a specific severe accident to investigate and developed a list of input uncertain parameters. NNEGC "ENERGOATOM" simulates a station blackout (SBO) at the first unit of South-Ukrainian NPP. OKB GIDROPRESS investigates a SBO scenario with account for accident management actions (opening of 3 PORVs 2 h since the initiating event).. IBRAE RAN has opted for LB LOCA (ACC injection line) that happens simultaneously with unmitigated SBO. NRC "KURCHATOV INSTITUTE" analyse LB LOCA (rupture of the pressurizer surge line) with simultaneous SBO. One paid attention to the justification of PDFs of uncertain input parameters giving preference to literary sources or technical documentation rather than expert judgment. The U&S analysis is mainly focused on in-vessel stage of severe accident progression and key FOMs at VVER-1000 reactor. Determined FOMs include hydrogen production, times of key events and other reactor and containment parameters. By now these institutions have obtained preliminary results on U&S analysis of selected FOMs and uncertainty associated with mesh refinement. The paper presents the description of the applied methodologies for U&S analysis, base case calculation results, and U&S analysis results performed by the group.
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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
- 8 p.
- Report number
- STI/PUB/2108
Conference
- Title International Conference on Topical Issues in Nuclear Installation Safety: Strengthening Safety of Evolutionary and Innovative Reactor Designs
- Dates
- 18-21 Oct 2022
- Place
- Vienna (Austria)
- Website https://www.iaea.org/events/tic-2022
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S97: MATHEMATICAL METHODS AND COMPUTING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- ACCIDENT MANAGEMENT; ATWS; CONTAINMENT; HYDROGEN PRODUCTION; IAEA; LOSS OF COOLANT; M CODES; MELTDOWN; REACTOR VESSELS; SENSITIVITY ANALYSIS; SEVERE ACCIDENTS; STATION BLACKOUT; TOOLS; US NRC; WATER COOLED REACTORS; WWER TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; EQUIPMENT; INTERNATIONAL ORGANIZATIONS; MANAGEMENT; NATIONAL ORGANIZATIONS; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SEVERE ACCIDENTS; THERMAL REACTORS; US ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 11 refs., 11 figs.
- Secondary number(s)
- IAEA-CN--308(SUPPLEMENTARY FILES)