Accident event progression, gaps, and key performance indicators for steam generator tube rupture events in water-cooled SMRs: A review
According to historical records of reactor-related incidents, a steam generator tube rupture
(SGTR) is one of the most common occurrences at operating pressurized water reactors …
(SGTR) is one of the most common occurrences at operating pressurized water reactors …
Safety assessment of AP1000: Common transients, analysis codes and research gaps
The commercial operation of the AP1000 in China's Sanmen nuclear power plant
demonstrates the feasibility of reactors with advanced passive safety systems. However …
demonstrates the feasibility of reactors with advanced passive safety systems. However …
SVR optimization with soft computing algorithms for incipient SGTR diagnosis
A Ayodeji, Y Liu - Annals of Nuclear Energy, 2018 - Elsevier
Fault severity awareness and fault identification are some of the key steps to a successful
diagnosis in nuclear power plants. Currently, faults such as leak detection are being done …
diagnosis in nuclear power plants. Currently, faults such as leak detection are being done …
PWR heat exchanger tube defects: trends, signatures and diagnostic techniques
A Ayodeji, Y Liu - Progress in Nuclear Energy, 2019 - Elsevier
In pressurized water reactor, one of the most important barriers to the release of radioactive
material to the environment is the steam generator heat exchanger tubes. Degradation of …
material to the environment is the steam generator heat exchanger tubes. Degradation of …
AP1000® SBLOCA simulations with TRACE code
J Montero-Mayorga, C Queral… - Annals of Nuclear …, 2015 - Elsevier
The AP1000® is an advanced pressurized water reactor (PWR) design developed by
Westinghouse which implements passive safety systems to provide core cooling in case of …
Westinghouse which implements passive safety systems to provide core cooling in case of …
Analysis of cold leg LOCA with failed HPSI by means of integrated safety assessment methodology
J Gonzalez-Cadelo, C Queral… - Annals of Nuclear …, 2014 - Elsevier
The integrated safety assessment (ISA) methodology, developed by the Spanish Nuclear
Safety Council (CSN), has been applied to a thermal–hydraulic analysis of cold leg LOCA …
Safety Council (CSN), has been applied to a thermal–hydraulic analysis of cold leg LOCA …
Influence of frequency content of ground motions on seismic fragility of equipment in nuclear power plant
Q Ma, OS Kwon, TH Kwon, YS Choun - Engineering Structures, 2020 - Elsevier
The objective of this study is to investigate the influence of frequency content of ground
motions on the seismic fragility of nuclear power plant (NPP) equipment. Transfer functions …
motions on the seismic fragility of nuclear power plant (NPP) equipment. Transfer functions …
Effects of delayed RCP trip during SBLOCA in PWR
J Montero-Mayorga, C Queral… - Annals of Nuclear …, 2014 - Elsevier
Abstract After the Three Mile Island (TMI) accident, the issue of when to trip the Reactor
Coolant Pumps (RCPs) in case of a Small Break Loss of Coolant Accident (SBLOCA) …
Coolant Pumps (RCPs) in case of a Small Break Loss of Coolant Accident (SBLOCA) …
Evaluation of the offsite dose contribution to the global risk in a Steam Generator Tube Rupture scenario
The current main figure of merit for risk based decision making process based on
Probabilistic Safety Assessment level 1 is usually related with the fuel failure (ie, Peak …
Probabilistic Safety Assessment level 1 is usually related with the fuel failure (ie, Peak …
[HTML][HTML] ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions
T Takeda - Nuclear Engineering and Technology, 2018 - Elsevier
An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test
facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a …
facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a …