Zobrazeno 1 - 10
of 130
pro vyhledávání: '"Hyun Gook Kang"'
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 7, Pp 1462-1470 (2020)
Reliability in safety-critical systems and equipment is of vital importance, so the probabilistic safety assessment (PSA) has been widely used for many years in the nuclear industry to address reliability in a quantitative manner. As many nuclear pow
Externí odkaz:
https://doaj.org/article/5110698e98d640fe8c09311dd3a664d9
Autor:
Xingang Zhao, Junyung Kim, Kyle Warns, Xinyan Wang, Pradeep Ramuhalli, Sacit Cetiner, Hyun Gook Kang, Michael Golay
Publikováno v:
Frontiers in Energy Research, Vol 9 (2021)
In a carbon-constrained world, future uses of nuclear power technologies can contribute to climate change mitigation as the installed electricity generating capacity and range of applications could be much greater and more diverse than with the curre
Externí odkaz:
https://doaj.org/article/2d06d57649a649899414a974395e0b93
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 3, Pp 692-701 (2019)
Recently, instrumentation and control (I&C) systems in nuclear power plants have undergone digitalization. Owing to the unique characteristics of digital I&C systems, the reliability analysis of digital systems has become an important element of prob
Externí odkaz:
https://doaj.org/article/bdd0cb9fb93041fb92ec0cd2622b5cdc
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 3, Pp 676-682 (2019)
After the Fukushima Daiichi accident, there has been an increasing preference for passive safety features in the nuclear power industry. Some passive safety systems require limited active components to trigger subsequent passive operation. Under very
Externí odkaz:
https://doaj.org/article/695445af60a74666b98eb2f0dc293d49
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 2, Pp 402-409 (2019)
When a loss of coolant accident (LOCA) occurs in a nuclear power plant, accident scenarios which can prevent core damage are defined based on break size. Current probabilistic safety assessment evaluates that core damage can be prevented under small-
Externí odkaz:
https://doaj.org/article/2fcf662ece094b87abd3b4e0ae410907
Publikováno v:
Nuclear Engineering and Technology, Vol 50, Iss 4, Pp 570-581 (2018)
Recently, a software program has been used in nuclear power plants (NPPs) to digitalize many instrumentation and control systems. To guarantee NPP safety, the reliability of the software used in safety-critical instrumentation and control systems mus
Externí odkaz:
https://doaj.org/article/e88aef7da83c4364b225878330f4312c
Publikováno v:
IEEE Access, Vol 6, Pp 8440-8451 (2018)
Software failure probability quantification is an important aspect of digital system reliability assessment. Several quantification methods currently available in the software reliability field have characteristics unsuitable for application to safet
Externí odkaz:
https://doaj.org/article/fff36e7eb73648e5a434ecfcac7cac5d
Autor:
Seung Jun Lee, Sang Hun Lee, Tsong-Lun Chu, Athi Varuttamaseni, Meng Yue, Ming Li, Jaehyun Cho, Hyun Gook Kang
Publikováno v:
IEEE Access, Vol 6, Pp 64556-64568 (2018)
Since digital instrumentation and control systems are expected to play an essential role in safety systems in nuclear power plants (NPPs), the need to incorporate software failures into NPP probabilistic risk assessment has arisen. Based on a Bayesia
Externí odkaz:
https://doaj.org/article/e73154764b0d4427a9268a162a85a5e1
Autor:
Mirae Yun, Robby Christian, Bo Gyung Kim, Belal Almomani, Jaehyun Ham, Sanghoon Lee, Hyun Gook Kang
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 4, Pp 721-733 (2017)
When temporary spent fuel storage pools at nuclear power plants reach their capacity limit, the spent fuel must be moved to an alternative storage facility. However, radioactive materials must be handled and stored carefully to avoid severe consequen
Externí odkaz:
https://doaj.org/article/7bf7e8a40e31468da736b28d378c0d5b
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 2, Pp 411-425 (2017)
Using a probabilistic safety assessment, a risk evaluation framework for an aircraft crash into an interim spent fuel storage facility is presented. Damage evaluation of a detailed generic cask model in a simplified building structure under an aircra
Externí odkaz:
https://doaj.org/article/9ba22ee33a244dd88b9c14f7c03ef3eb