2019-Sustainable Industrial Processing Summit
SIPS2019 Volume 12: Energy Production and Secondary Batterie
| Editors: | F. Kongoli, H. Dodds, M. Mauntz, T. Turna, K. Aifantis, A. Fox, V. Kumar |
| Publisher: | Flogen Star OUTREACH |
| Publication Year: | 2019 |
| Pages: | 112 pages |
| ISBN: | 978-1-989820-11-7 |
| ISSN: | 2291-1227 (Metals and Materials Processing in a Clean Environment Series) |
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Dynamic Probabilistic Risk Assessment of Nuclear Reactor Operation
Tunc Aldemir1;1THE OHIO STATE UNIVERSITY, Columbus, United States;
Type of Paper: Keynote
Id Paper: 183
Topic: 17
Abstract:
Introduced in the 70s, the traditional approach to probabilistic risk assessment (PRA) of a nuclear reactor operation is the event-tree/fault-tree approach (ET/FT). The ET/FT approach only qualitatively accounts for the timing of events through their ordering. A new generation of methodologies is starting to receive attention for the nuclear reactor PRA. Often referred to as dynamic PRA (DPRA) methodologies1, these methodologies explicitly account for the time element in the probabilistic system evolution and heavily incorporate plant analysis tools (e.g., RELAP2, MELCOR3, MAAP54) to model possible dependencies among failure events that may arise from hardware/software/firmware/process/ human interactions. DPRA methodologies are also capable of quantifying the effects of phenomenological variability and model uncertainties on the consequences of upset conditions. They can be particularly useful for the PRA modeling of passive safety systems, including representation of aging effects. An overview of the DPRA methodologies is presented, including system level applicable computational tools.
Keywords:
Energy; Engineering;References:
1. T. Aldemir, "A Survey of Dynamic Methodologies for Probabilistic Safety Assessment of Nuclear Power Plants", Annals of Nuclear Engineering, 52, 113-124 (2013).2. The RELAP5-3D Code Development Team, RELAP5-3D Code Manual, Volume I: Code Structure, System Models, and Solution Methods, INEEL-EXT-98-00834, June 2005.
3. R. O. Gauntt et al., "MELCOR Computer Code Manuals," NUREG/CR-6119, Vol.2, Rev. 3 (SAND2005-5713), U.S. Nuclear Regulatory Commission, Washington, D.C. (2005).
4. Modular Accident Analysis Program - MAAP5 v5.04 for Windows, 3002007340, EPRI, Palo Alto, CA. September 2016 (2016).