A model for operational risk of nuclear fuel cycle facilities including ageing, test degradation effects and maintenance effectiveness

Published: 7 March 2024| Version 1 | DOI: 10.17632/xck298ysc9.1
Contributors:
Saulo Fernando Quintão Ribeiro, José de Jesús Rivero Oliva

Description

This database describes the main data and results of the dynamic unavailability/risk model for two application cases. In both application cases the results of the Dynamic Model (identified as Detailed Assessment - DA) is compared with the Standard PSA, based on components mean unavailabilities, and also with the Conventional Assessment (CA) that uses the same mean unavailability models corrected by instantaneous unavailability values at the specific time intervals of components outage due to maintenances and tests. The Detailed Assessment (DA) was evaluated considering different scenarios of components ageing, test degradation, test efficiency and maintenance effectiveness not included in the Conventional Assessment (CA) approach. The data base is compound by pdf files with the main data and results of the two application cases: 1. Large Break Loss of Coolant Accident (LBLOCA) in a Pressurized Water Reactor (PWR) 2. Risk analysis of a total loss of the safety ventilation system of an underground uranium mine as a consequence of a Loss of Offsite Power (LOSP) initiating event. The information of each application case is structured as follows: - Standard PSA . Basic events and Reliability data . Fault Tree . Base risk and most important Minimal Cut Sets . Importance analysis (Fussell-Vesely and RAW) - Operational history data for CA and DA - Basic events and Reliability data for CA and DA - Conventional Assessment (CA) . Time-dependent Risk assessment (Table and chart) . Importance analysis (Fussell-Vesely and RAW) . Time-dependent Importance Analysis for selected components (Tables and charts) - Detailed Assessment (DA) . Time-dependent Risk assessment for different scenarios of components ageing, test degradation, test efficiency and maintenance effectiveness (Tables and charts) . Importance analysis for different scenarios of components ageing, test degradation, test efficiency and maintenance effectiveness (Fussell-Vesely and RAW) . Time-dependent Importance Analysis for selected components for different scenarios of components ageing, test degradation, test efficiency and maintenance effectiveness (Tables and charts)

Files

Institutions

Universidade Federal do Rio de Janeiro

Categories

Risk Analysis, Aging, Safety, Mining, Mining Engineering, Dynamic Modeling, Probabilistic Safety Assessment

Licence