Zobrazeno 1 - 10
of 19
pro vyhledávání: '"Kukhee Lim"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 10, Pp 4018-4030 (2024)
The in-vessel retention through external reactor vessel cooling (IVR-ERVC) strategy is a key management strategy for early termination of a nuclear severe accident that can threaten the integrity of the reactor vessel. To simulate the physical phenom
Externí odkaz:
https://doaj.org/article/d36acc8b501e429d89fbe1e4bc9f7aab
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 7, Pp 2859-2874 (2024)
This paper presents the finite element deformation and failure simulation of a typical Korean high-power reactor vessel under a severe accident characterized by large break loss of coolant (LBLOCA) with in-vessel retention of molten corium through ex
Externí odkaz:
https://doaj.org/article/8e7545a1c2a1418491e4c83bca3bdc17
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 11, Pp 4146-4158 (2023)
This paper proposes a combined plastic and creep constitutive model of A533B1 pressure vessel steel to simulate progressive deformation of nuclear pressure vessels under severe accident conditions. To develop the model, recent tensile test data cover
Externí odkaz:
https://doaj.org/article/726d79f802d84627a2352a84de709526
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 11, Pp 4134-4145 (2023)
This paper proposes strain-based failure model of A533B1 pressure vessel steel to simulate failure, followed by application to OECD lower head failure (OLHF) test simulation for experimental validation. The proposed strain-based failure model uses si
Externí odkaz:
https://doaj.org/article/92154ed2de0c48ed9908f2f477acc521
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 9, Pp 3241-3251 (2023)
The potential for recriticality and sub-critical boron concentrations is analyzed during the relocation of the fuel rods in the assembly, which we call late phase of a severe accident, via coupling between MELCOR and whole-core Monte Carlo analyses b
Externí odkaz:
https://doaj.org/article/0688657a78674ea3801191e3f14e7f50
Autor:
Jongtae Kim, Kukhee Lim
Publikováno v:
Applied Sciences, Vol 14, Iss 15, p 6695 (2024)
In a pressurized water reactor (PWR) during a loss of coolant accident (LOCA) or a station blackout (SBO) accident, water and steam are released into the containment building. The water vapor mixes with the atmosphere, partially condensing into dropl
Externí odkaz:
https://doaj.org/article/9a86889e67f544459dd3c9c81bebda1c
Autor:
Jang Min Park, Kukhee Lim
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 12, Pp 4522-4533 (2022)
For severe accident assessment of reactor pressure vessel (RPV), it is important to develop an accurate model that can predict transient thermo-mechanical behavior of the RPV lower head under the given condition. The present study revisits the lower
Externí odkaz:
https://doaj.org/article/fccc2c09ca41418eb0255eb5b0ed923e
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 7, Pp 2690-2701 (2022)
In this paper, we select important fission products for the estimation of the source term during a severe accident of a PWR. The selection is based on the numerical results obtained from depletion calculations for the typical PWR fuel via the in-hous
Externí odkaz:
https://doaj.org/article/32ad5dd72d074ff694a9f703ec59cbcf
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2022 (2022)
The rupturing of steam generator tubes leads to serious accidents in nuclear power plants. It causes radioactive materials to leak into the secondary system and release outside the reactor containment region. Therefore, it is important to model a tec
Externí odkaz:
https://doaj.org/article/603c89e956bf49dba708a2c471718743
Publikováno v:
International Journal of Hydrogen Energy. 47:38395-38406
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::9cbdadef7c5de69a00fb50b0dbf08f01
https://doi.org/10.1016/j.ijhydene.2022.08.311
https://doi.org/10.1016/j.ijhydene.2022.08.311