Published 2017 | Version v1
Miscellaneous Open

Quantitative Evaluation of the Post Disassembly Energetics of a Hypothetical Core Disruptive Accident in a Sodium Cooled Fast Reactor

  • 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)

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Part of:
International Conference on Fast Reactors and Related Fuel Cycles: Next Generation Nuclear Systems for Sustainable Development (FR17). Programme and Papers

Additional details

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