Quantitative Evaluation of the Post Disassembly Energetics of a Hypothetical Core Disruptive Accident in a Sodium Cooled Fast Reactor
Creators
- 1. Karlsruhe Institute of Technology (KIT), Eggenstein-Leopoldshafen (Germany)
Description
Analyses of Hypothetical Core Disruptive Accidents (HCDAs) play a fundamental role in the safety assessment of Sodium Fast Reactors (SFRs). The accident sequence is typically subdivided into different phases according to dominant phenomena. The phase dealing with an upward discharge of the pressurized hot fuel/steel mixture from the core region is referred as the Post-Disassembly Expansion (PDE) phase. It is characterized by massive sodium vaporization due to Fuel-Coolant Interaction (FCI) in the upper sodium pool, which displaces and accelerates the surrounding liquid sodium resulting in potential significant loads on internal structures and vessel. The present paper - based on KIT simulations with the SIMMER code including dedicated parametric studies - identifies and evaluated the main PDE phenomena and event paths enhancing or mitigating the mechanical work potential. (author)
Files
49085701.pdf
Files
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Additional details
Identifiers
Publishing Information
- Imprint Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Programme and Papers
- Imprint Pagination
- vp.
- Journal Page Range
- 10 p.
- Report number
- IAEA-CN--245
Conference
- Title
- International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development
- Acronym
- FR17
- Dates
- 26-29 Jun 2017
- Place
- Yekaterinburg (Russian Federation)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 49085701
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FUEL-COOLANT INTERACTIONS; LMFBR TYPE REACTORS; PARAMETRIC ANALYSIS; REACTOR CORE DISRUPTION; RISK ASSESSMENT; SODIUM COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; BEYOND-DESIGN-BASIS ACCIDENTS; BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTOR ACCIDENTS; REACTORS; SEVERE ACCIDENTS
Optional Information
- Notes
- 29 refs., 9 figs., 3 tabs.
- Secondary number(s)
- IAEA-CN--245-483