A review of the FLEX strategy for nuclear safety

H Xu, B Zhang - Nuclear Engineering and Design, 2021 - Elsevier
After the Fukushima nuclear accident, in order to enhance the implementation strategy of
Defence in Depth (DID) for nuclear safety and response to the US Nuclear Regulatory …

Risk reduction by means of FLEX strategies in pressurized water reactors

S Courtin, C Queral, A García-Herranz - Nuclear Engineering and Design, 2023 - Elsevier
One of the key lessons learned from the Fukushima Dai-ichi accident was the importance of
the challenge presented by the loss of safety-related systems after a Beyond Design-Basis …

Activities in Spain on the integration of probabilistic and deterministic safety analysis methods. Discussion on their applicability to DEC-A scenarios

R Mendizábal, M Sánchez, C Queral, J Hortal… - … Engineering and Design, 2024 - Elsevier
This paper presents a summary of theoretical and applied achievements in the field of
integrated methods of nuclear safety analysis produced by Spain's nuclear safety …

Quantitative risk reduction by means of recovery strategies

C París, C Queral, J Mula, J Gómez-Magán… - Reliability Engineering & …, 2019 - Elsevier
After the accident at Fukushima Dai-ichi, considerable efforts were put on enhancing the
capability of the Nuclear Power Plants to cope with conditions resulting from the loss of plant …

Analysis of a LBLOCA with FLEX actuations in a PWR-W

K Fernandez-Cosials, C Queral, F Robledo… - … Engineering and Design, 2020 - Elsevier
Abstract After the Fukushima-Daiichi accident, different methods, strategies and guidelines
were developed to improve the Severe Accident Management Guidelines (SAMG). One of …

Dynamic probabilistic risk assessment of seismic-induced flooding in pressurized water reactor by seismic, flooding, and thermal-hydraulics simulations

K Kubo, S Jang, T Takata… - Journal of Nuclear …, 2023 - Taylor & Francis
Probabilistic risk assessment (PRA) is an essential approach to improving the safety of
nuclear power plants. However, this method includes certain difficulties, such as modeling of …

Quasi-Monte Carlo sampling method for simulation-based dynamic probabilistic risk assessment of nuclear power plants

K Kubo, S Jang, T Takashi… - Journal of Nuclear …, 2022 - Taylor & Francis
Dynamic probabilistic risk assessment (PRA), which handles epistemic and aleatory
uncertainties by coupling the thermal-hydraulics simulation and probabilistic sampling …

[HTML][HTML] Optimization of prevention and mitigation of severe accidents through Research: Major outcomes and outlook of the Spanish programme

LE Herranz, A Domínguez-Bugarín… - … Engineering and Design, 2024 - Elsevier
Severe accidents research activities in Spain have grown substantially since the Fukushima-
Daiichi accident. Most of these research activities have been conducting by a few …

Quantification of risk dilution induced by correlation parameters in dynamic probabilistic risk assessment of nuclear power plants

K Kubo, Y Tanaka, J Ishikawa - … , Part O: Journal of Risk and …, 2024 - journals.sagepub.com
Nuclear power plants are critical infrastructures that produce electricity. However, accidents
in nuclear power plants can cause considerable consequences such as the release of …

Reactor Coolant Pump Leakage Estimation of PWR Based on Broad Learning System

C Wang, J Liu - Journal of Physics: Conference Series, 2021 - iopscience.iop.org
Loss-of-coolant accident (LOCA) of reactor coolant pump is considered as a critical issue in
pressurized water reactor (PWR) accident analysis. Much work focus on the detection of …