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of 9
pro vyhledávání: '"Young Gyu No"'
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 2, Pp 386-403 (2016)
The safety of nuclear power plants is analyzed by a probabilistic risk assessment, and the fault tree analysis is the most widely used method for a risk assessment with the event tree analysis. One of the well-known disadvantages of the fault tree is
Externí odkaz:
https://doaj.org/article/aedbb31cf0ad4ad5b34af79411b7b125
Publikováno v:
Nuclear Engineering and Technology, Vol 47, Iss 1, Pp 74-84 (2015)
If a transient occurs in a nuclear power plant (NPP), operators will try to protect the NPP by estimating the kind of abnormality and mitigating it based on recommended procedures. Similarly, operators take actions based on severe accident management
Externí odkaz:
https://doaj.org/article/a3d55f15e68847b38c6d1ee3d5d5e0b9
Publikováno v:
Annals of Nuclear Energy. 126:186-193
Since the Fukushima nuclear accident in 2011, there has been a growing need to strengthen severe accident management guidelines (SAMGs) and find appropriate methods for validating SAMGs. The validation of SAMGs is currently performed in terms of thei
Publikováno v:
Annals of Nuclear Energy. 122:317-327
The margin of human action time from severe accident management guideline (SAMG) entrance to reactor vessel (RV) failure was analyzed to compare the required human action time and available human action time based on a severe accident DB developed us
Publikováno v:
Annals of Nuclear Energy. 121:552-566
The importance of severe accident management is being re-examined because severe accident management failed during the Fukushima nuclear accident. Having an accurate estimation of a severe accident is important for coping properly with unfavorable co
Publikováno v:
Nuclear Engineering and Technology. 44:393-404
After the Fukushima nuclear accident in 2011, there has been increasing concern regarding severe accidents in nuclear facilities. Severe accident scenarios are difficult for operators to monitor and identify. Therefore, accurate prediction of a sever
Autor:
Young Gyu No, Sim Won Lee, Sung Han Lee, Dong-Hoon Kim, Changheui Jang, Man Gyun Na, Jae Yong Lee, Dong Su Kim
Publikováno v:
Nuclear Engineering and Technology. 43:301-308
The diametral creep of pressure tubes (PTs) in CANDU (CANada Deuterium Uranium) reactors is one of the principal aging mechanisms governing the heat transfer and hydraulic degradation of the heat transport system (HTS). PT diametral creep leads to di
Publikováno v:
IEEE Transactions on Nuclear Science. 58:267-276
As a means of effectively managing severe accidents at nuclear power plants, it is important to identify and diagnose accident initiating events within a short time interval after the accidents by observing the major measured signals. The main object
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 2, Pp 386-403 (2016)
The safety of nuclear power plants is analyzed by a probabilistic risk assessment, and the fault tree analysis is the most widely used method for a risk assessment with the event tree analysis. One of the well-known disadvantages of the fault tree is