Zobrazeno 1 - 10
of 24
pro vyhledávání: '"Kwang-Seop Son"'
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 8, Pp 2952-2965 (2023)
Advanced reactors, such as Small Modular Reactors or existing Nuclear Power Plants, often use Field Programmable Gate Array (FPGA) based controllers in new Instrumentation and Control (I&C) system architectures or as an alternative to existing analog
Externí odkaz:
https://doaj.org/article/b6fb5addd5974af7bea3b19a4e6de32a
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 6, Pp 2034-2046 (2023)
Industrial control systems in nuclear facilities are facing increasing cyber threats due to the widespread use of information and communication equipment. To implement cyber security programs effectively through the RG 5.71, it is necessary to quanti
Externí odkaz:
https://doaj.org/article/49f57b883bcf48a6b2e5a456dd84c652
Publikováno v:
12th Nuclear Plant Instrumentation, Control and Human-Machine Interface Technologies (NPIC&HMIT 2021).
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b77b33a06ad49b7e12f4758b6849d87b
https://doi.org/10.13182/t124-36328
https://doi.org/10.13182/t124-36328
Publikováno v:
Annals of Nuclear Energy. 111:73-81
We analyze the availability of the Safety Programmable Logic Controller (SPLC) having multiple redundant architectures. In the SPLC, input/output and processor module are configured as triple modular redundancy (TMR), and backplane bus, power and com
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c427a2a4985e5aee8da0ae39519cfe87
https://doi.org/10.1016/j.anucene.2017.08.065
https://doi.org/10.1016/j.anucene.2017.08.065
Publikováno v:
Annals of Nuclear Energy. 108:394-405
As one of the safety-critical systems in nuclear power plants (NPPs), the Engineered Safety Feature-Component Control System (ESF-CCS) employs safety data link and network communication for the transmission of safety component actuation signals from
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::d59f06fffb417b764594ba1df5be1582
https://doi.org/10.1016/j.anucene.2017.04.025
https://doi.org/10.1016/j.anucene.2017.04.025
Publikováno v:
Reliability Engineering & System Safety. 150:44-57
The Markov analysis is a technique for modeling system state transitions and calculating the probability of reaching various system states. While it is a proper tool for modeling complex system designs involving timing, sequencing, repair, redundancy
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::52f5ce4cbe9915826cd4e87398ece27b
https://doi.org/10.1016/j.ress.2016.01.014
https://doi.org/10.1016/j.ress.2016.01.014
Publikováno v:
Reliability Engineering & System Safety. 144:285-295
The Engineered Safety Feature-Component Control System (ESF-CCS), which uses a network communication system for the transmission of safety-critical information from group controllers (GCs) to loop controllers (LCs), was recently developed. However, t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7596a346d9574077c492747e580cecaa
https://doi.org/10.1016/j.ress.2015.07.029
https://doi.org/10.1016/j.ress.2015.07.029
Publikováno v:
Annals of Nuclear Energy. 142:107409
We present effective periodic surveillance test (PST) strategies enhancing the availability of nuclear safety systems with three-channel configuration in PWR (Pressurized Water Reactor), which can be used in limited space applications. The suggested
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ac38c852d8bb693faab3b0989c98261b
https://doi.org/10.1016/j.anucene.2020.107409
https://doi.org/10.1016/j.anucene.2020.107409
Publikováno v:
Reliability Engineering & System Safety. 193:106645
In the design process of safety critical digital systems, the quantitative analysis of their dependability is essential step to enhance the safety of nuclear power plants. Earlier this analysis can be performed, higher safety can be achieved in a mor
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::42c905e9a53fd49ad48c2a58d905f084
https://doi.org/10.1016/j.ress.2019.106645
https://doi.org/10.1016/j.ress.2019.106645
Publikováno v:
Annals of Nuclear Energy. 76:367-377
The Fukushima accident induced by the great earthquake and tsunami reveals the vulnerability of I&C System. In the severe environment, the normal I&C system did not work properly and results in false information about the internal situation in NPP. E
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e20765d6e06ecbd9bd6bfcb46d7898fd
https://doi.org/10.1016/j.anucene.2014.10.008
https://doi.org/10.1016/j.anucene.2014.10.008