Uncertainty-Based Validation Methodology and Experimental Analysis for External Control Room Human Performance Simulation: Application to Fire Probabilistic Risk Assessment of Nuclear Power Plants-Reference-Cited by-同舟云学术

Uncertainty-Based Validation Methodology and Experimental Analysis for External Control Room Human Performance Simulation: Application to Fire Probabilistic Risk Assessment of Nuclear Power Plants

Published:2024-07 Issue: Volume: Page:1-20
ISSN:0029-5639
Container-title:Nuclear Science and Engineering
language:en
Short-container-title:Nuclear Science and Engineering

Author:

Albati Mohammad¹^ORCID,Sakurahara Tatsuya¹,Reihani Seyed¹,Kee Ernie¹,Yang Jaemin¹,von Thaden Terry²,Kesler Richard²³,Masoud Farzaneh²,Mohaghegh Zahra¹

Affiliation:

1. University of Illinois at Urbana-Champaign, Grainger College of Engineering, Department of Nuclear, Plasma, and Radiological Engineering, Socio-Technical Risk Analysis (Soteria) Research Laboratory, 104 S. Wright Street, Urbana, Illinois 61801

2. University of Illinois at Urbana-Champaign, Illinois Fire Service Institute, 11 Gerty Drive, Champaign, Illinois 61820

3. Fire Safety Research Institute, UL Research Institutes, 6200 Old Dobbin Lane, Columbia, Maryland 21045

Funder

U.S. Department of Energy

Publisher

Informa UK Limited

Link

https://www.tandfonline.com/doi/pdf/10.1080/00295639.2024.2366735

Reference51 articles.

1. On The Quantitative Definition of Risk

2. P. V. VARDE and M. G. PECHT, Risk-Based/Risk-Informed Applications, in Risk-Based Engineering: An Integrated Approach to Complex Systems—Special Reference to Nuclear Plants, P. V. VARDE and M. G. PECHT, Eds. pp. 531–560, Springer Singapore (2018).

3. S. ATSUJI et al., “Fukushima Nuclear Catastrophe 3.11: System Pathology of Social Organizations” Proc. 55th Annual Mtg. of the ISSS, Hull (2011).

4. The accident at TEPCO's Fukushima-Daiichi Nuclear Power Station: What went wrong and what lessons are universal?

5. Probabilistic Reactor Dynamics — III. A Framework for Time-Dependent Interaction between Operator and Reactor during a Transient Involving Human Error