Zobrazeno 1 - 10
of 105
pro vyhledávání: '"Myung-Jo Jhung"'
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 5, Pp 1577-1586 (2023)
Safety qualification of a steam generator is a crucial issue related to faulted condition design loads, including earthquake loads, and it should be ensured that the structural integrity of a steam generator does not exceed its design load. Using dat
Externí odkaz:
https://doaj.org/article/f14a9c9fab8a450f95649fba2dd95caf
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 9, Pp 3353-3360 (2022)
Using data from the design earthquake of the Korean standard nuclear power plant, seismic analyses of a fuel assembly are conducted in this study. The modal characteristics are used to develop an input deck for the seismic analysis. With a time histo
Externí odkaz:
https://doaj.org/article/a290ed3062a84aad814e7300959027ff
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 1, Pp 401-413 (2022)
This paper provides a simple method by which to estimate the cross-section stress profiles for nozzles designed according to ASME Code Section III. Further, this method validates the effectiveness of earlier work performed by the authors on standard
Externí odkaz:
https://doaj.org/article/f6e6aadb2df74818aad534bc3a0f6b81
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 8, Pp 2716-2727 (2021)
The core shroud is one of the most important internal components of the reactor vessel internals because it meets the neutron fluence directly emitted by the nuclear fuel. In particular, dynamic effects for an earthquake should be evaluated with resp
Externí odkaz:
https://doaj.org/article/108bc19263e64990b5775b65773906fc
Publikováno v:
Nuclear Engineering and Technology, Vol 52, Iss 1, Pp 185-191 (2020)
Plant-specific analyses of an advanced reactor have been performed to assure the structural integrity of the reactor pressure vessel during transient conditions, which are expected to initiate pressurized thermal shock (PTS) events. The vessel failur
Externí odkaz:
https://doaj.org/article/6558a741997f407dab558e6925492c6d
Autor:
Myung Jo Jhung, Sung-Sik Kang
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 4, Pp 1117-1131 (2019)
Tanks are used extensively in many engineering areas for spent fuel pool structures at nuclear power plants or for water storage tanks in bulk carriers. To ensure the structural integrity of such tanks when under dynamic loads, modal characteristics
Externí odkaz:
https://doaj.org/article/a2341fee3269471da0f0f1d6d158bdad
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 3, Pp 651-661 (2017)
The Korea Institute of Nuclear Safety, as a representative organization of Korea, in February 2012 participated in an international Program to Assess the Reliability of Emerging Nondestructive Techniques initiated by the U.S. Nuclear Regulatory Commi
Externí odkaz:
https://doaj.org/article/27b2f33281a34bd6913c227cb8021b76
Autor:
Kyeong Hoon Jeong, Myung Jo Jhung
Publikováno v:
Nuclear Engineering and Technology, Vol 49, Iss 1, Pp 234-244 (2017)
Natural frequencies of immersed square sections decrease due to a contribution of added mass to the movement of square sections. In this study, natural frequencies of square sections are obtained as a function of gap size between the square section a
Externí odkaz:
https://doaj.org/article/37fc580787c0420a8e4867117ec958bb
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 2, Pp 545-553 (2016)
The failure probabilities of the reactor pressure vessel (RPV) for low temperature over-pressurization (LTOP) and cool-down transients are calculated in this study. For the cool-down transient, a pressure–temperature limit curve is generated in acc
Externí odkaz:
https://doaj.org/article/675b670335534f5e8a3b9eae99ea83ea
Publikováno v:
Nuclear Engineering and Technology, Vol 48, Iss 1, Pp 218-227 (2016)
Background: Steam explosions may occur in nuclear power plants by molten fuel–coolant interactions when the external reactor vessel cooling strategy fails. Since this phenomenon can threaten structural barriers as well as major components, extensiv
Externí odkaz:
https://doaj.org/article/ddcf18f134db4819b7aea871b95d8f25