Zobrazeno 1 - 10
of 117
pro vyhledávání: '"MARS-KS"'
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 8, Pp 3435-3449 (2024)
Considering that system analysis codes are used for the evaluation of the performance of Passive Safety Systems (PSSs), it is important to investigate the capability of the system analysis code to reliably predict the heat transfer and natural circul
Externí odkaz:
https://doaj.org/article/7fa2b32f71ca4f7a9aa24651c0f0b795
Autor:
Hyunjoon Jeong, Taewan Kim
Publikováno v:
Nuclear Engineering and Technology, Vol 56, Iss 6, Pp 2002-2010 (2024)
Korea Atomic Energy Research Institute (KAERI) has operated an integral effect test facility, the Advanced Thermal-Hydraulic Test Loop for Accident Simulation (ATLAS), with reference to the APR1400 (Advanced Power Reactor 1400) for tests for transien
Externí odkaz:
https://doaj.org/article/476aac84b70546beaec2a3639e9e1052
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 12, Pp 4335-4349 (2023)
Nuclear marine propulsion has been emerging as a next generation carbon-free power source, for which proper passive residual heat removal systems (PRHRSs) are needed for long-term safety. In particular, the characteristics of unlimited operation time
Externí odkaz:
https://doaj.org/article/0c2a46171fb7479e98a9fe9f3d0f63ea
Autor:
Yunseok Lee, Taewan Kim
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 12, Pp 4357-4366 (2023)
MARS-KS, a domestic regulatory confirmatory code of Republic of Korea, had been developed by integrating RELAP5/MOD2 and COBRA-TF. The integration of COBRA-TF allowed to extend the capability of MARS-KS, limited to one-dimensional analysis, to multi-
Externí odkaz:
https://doaj.org/article/16fc210136ec4a9db2862e4c47905c47
Publikováno v:
Nuclear Engineering and Technology, Vol 55, Iss 12, Pp 4607-4616 (2023)
We implement machine learning regression models to predict peak pressures of primary and secondary systems, a major safety concern in Loss Of Condenser Vacuum (LOCV) accident. We selected the Multi-dimensional Analysis of Reactor Safety-KINS standard
Externí odkaz:
https://doaj.org/article/9e19faadf3af4fbfa92690e9c580a3a9
Moving reactor model for the MULTID components of the system thermal-hydraulic analysis code MARS-KS
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 11, Pp 4373-4391 (2022)
Marine reactor systems experience platform movement, and therefore, the system thermal-hydraulic analysis code needs to reflect the motion effect on the fluid to evaluate reactor safety. A moving reactor model for MARS-KS was developed to simulate th
Externí odkaz:
https://doaj.org/article/025a4d2f66a949c8b2a577c243a2626c
Akademický článek
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Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 5, Pp 1698-1711 (2022)
A combined safety approach, which uses a best-estimate computer code and adopts conservative assumptions for safety systems availability, is developed and applied to the safety margin evaluation for the Loss of Condenser Vacuum (LOCV) of the 1000 MWe
Externí odkaz:
https://doaj.org/article/018dc3eb22034c42a1b961308cc4c694
Autor:
Seon Oh YU, Manwoong KIM
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 10, Pp 3236-3246 (2021)
Lessons learned from the Fukushima Daiichi nuclear power plant accident directed that multiple failures should be considered more seriously rather than single failure in the licensing bases and safety cases because attempts to take accident managemen
Externí odkaz:
https://doaj.org/article/5829e07dd2c8431f87b7ca7d39268bde
Autor:
Yeon-Gun Lee, Sang Gyu Lim
Publikováno v:
Nuclear Engineering and Technology, Vol 53, Iss 10, Pp 3196-3206 (2021)
For the Korean design of the PCCS (passive containment cooling system) in an innovative PWR, the overall thermal resistance around a condenser tube is dominated by the heat transfer coefficient of steam condensation on the exterior surface. It has be
Externí odkaz:
https://doaj.org/article/a4472427767c48bea89148ddbb7a058d