Development of a hybrid method to assess grid-related LOOP scenarios for an NPP
Creators
- 1. School of Mechanical Engineering, Shiraz University Shiraz 71936-16548 (Iran, Islamic Republic of)
- 2. Safety Research Center of Shiraz University, Shiraz 71936-16548 (Iran, Islamic Republic of)
- 3. Université Libre de Bruxelles, Bruxelles B1050 (Belgium)
Description
Highlights: • Hybrid Method is developed to investigate GR-LOOP progression in IEEE test grid. • The PSA module develops the sequences upon a 3Ph-SC fault on each transmission line. • Dynamic simulation module evaluates the security parameters of related scenarios. • LOOP sequences are identified upon 3Ph-SC faults on four transmission lines. • Methodology can replace generic data to estimate the grid-dependent LOOP frequency. Loss of Offsite Power (LOOP) is the most dominant initiating event in the Core Damage Frequency (CDF) of Nuclear Power Plants (NPPs). Since the frequency of occurrence of LOOP depends on the grid configuration, outage schedule, load flow, etc., even a relevant generic frequency may result in significant uncertainty. In this study, an analytical hybrid methodology, which combines the probabilistic and deterministic modules, is introduced to systematically estimate the frequency of Grid-related LOOP. The proposed probabilistic module develops the relevant event-trees and fault-trees in SAPHIRE7 to identify the LOOP sequences upon the response of the distance protection system to a fault on the transmission lines. Meanwhile, the identified scenarios are confirmed based on the simulation results from the deterministic module in DIgSILENT-PowerFactory15.1. 15-out-of-48 scenarios (100-out-of-300 sequences) are identified as grid-related LOOP upon faults on the four transmission lines of the test grid, and result in 1.76E-06/yr for the grid-related LOOP frequency. The developed methodology enables us to trace a LOOP chain, from a primitive presumed fault through the progress of the cascade. The grid-related LOOP scenarios in a certain network can be ranked probabilistically, with the desired level of details in both deterministic and probabilistic modules.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.ress.2020.107298Additional details
Identifiers
- DOI
- 10.1016/j.ress.2020.107298;
- PII
- S0951832020307948;
Publishing Information
- Journal Title
- Reliability Engineering and System Safety
- Journal Volume
- 206
- Journal Page Range
- vp.
- ISSN
- 0951-8320
- CODEN
- RESSEP
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 54018507
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S43: PARTICLE ACCELERATORS;
- Descriptors DEI
- COMPUTERIZED SIMULATION; FAULT TREE ANALYSIS; NUCLEAR POWER PLANTS; OUTAGES; POWER TRANSMISSION LINES; PROBABILISTIC ESTIMATION; REACTOR SAFETY
- Descriptors DEC
- CALCULATION METHODS; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; SIMULATION; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL POWER PLANTS
Optional Information
- Copyright
- Copyright (c) 2020 Elsevier Ltd. All rights reserved.