Published 2017 | Version v1
Miscellaneous Open

Dynamic probabilistic risk assessment at a design stage for a sodium fast reactor

  • 1. EDF R&D, EDF Lab Paris-Saclay, Palaiseau (France)

Description

Sodium Fast Reactor is a good candidate for an application of dynamic probabilist risk assessment due to long mission times and possible system recoveries. In this paper, we present a new approach to construct the dynamic probabilistic model of the Decay Heat Removal (DHR) function of a Sodium Fast Reactor. We use Distributed Stochastic Hybrid Automata concept with the PyCATSHOO modeling tool. The proposed approach allows to construct a dynamic probabilistic model of a SFR DHR function that incorporates the time evolution of physical parameters and dynamic changes in the states of DHR systems (failure or recovery of DHR system components) and presents enough flexibility to be applied at the design stage. (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
8 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
49085736
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; FAST REACTORS; PROBABILISTIC ESTIMATION; RISK ASSESSMENT; SODIUM COOLED REACTORS
Descriptors DEC
CALCULATION METHODS; EPITHERMAL REACTORS; LIQUID METAL COOLED REACTORS; REACTORS; REMOVAL

Optional Information

Notes
9 refs., figs., 1 tab.
Secondary number(s)
IAEA-CN--245-042