Published 2022
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Multi-Unit Probabilistic Risk Assessment (MUPRA) for the PRISM Sodium Cooled Fast Reactor
Description
This paper describes the development of a multi-unit probabilistic risk assessment (MUPRA) for a Power Reactor Inherently Safe Module (PRISM) power block with two identical reactor units. The analysed PRISM design includes a single turbine/generator (T/G) fed from the two reactors, through a common steam inlet to the T/G. The goal of this MUPRA is to develop an analysis of events that involve more than one reactor on a multi-unit site for a non-LWR PRA.
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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
- 15 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)
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;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BEYOND-DESIGN-BASIS ACCIDENTS; FAST REACTORS; LMFBR TYPE REACTORS; MODULAR STRUCTURES; POWER LOSSES; PROBABILISTIC ESTIMATION; REACTOR ACCIDENTS; REACTOR SAFETY; RISK ASSESSMENT; SAFETY ANALYSIS; SODIUM; SODIUM COOLED REACTORS; STEAM; STEAM LINES; STEAM SYSTEMS; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BREEDER REACTORS; CALCULATION METHODS; ELEMENTS; ENERGY LOSSES; ENERGY SYSTEMS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LOSSES; METALS; PIPELINES; REACTORS; SAFETY
Optional Information
- Notes
- 7 refs., 6 figs., 5 tabs.
- Secondary number(s)
- IAEA-CN--308(SUPPLEMENTARY FILES)