Results 11 to 20 of about 176 (127)
THERMAL-HYDRAULIC TESTS AND ANALYSES FOR THE APR1400'S DEVELOPMENT AND LICENSING [PDF]
Nuclear Engineering and Technology, 2007 Development of the APR1400, an evolutionary typeof pressurized water reactor (PWR), was completed atthe end of 2001 and its standard design was approved inMay 2002 [1]. Recently, a contract was signed for theconstruction for the first unit (SKN Unit #3), the commercialoperation of which will commence in 2013.
Chul-Hwa Song, Won-Pil Baek
exaly +2 more sources
Science and Technology of Nuclear InstallationsOn September 2021, Polish government declared that six pressurized water reactors with combined capacity of 6–9 GWe will be built by 2040 to reduce Poland’s reliance on coal. Due to the adopted schedule, construction of the first nuclear power plant will
Edyta Agata Macieja, Juyoul Kim
doaj +2 more sources
Time-Series Forecasting of a Typical PWR Undergoing Large Break LOCA
Science and Technology of Nuclear InstallationsIn this work, a machine learning (ML) metamodel is developed for the time-series forecasting of a typical nuclear power plant response undergoing a loss of coolant accident (LOCA). The plant model of choice is based on the APR1400 nuclear reactor.
Michal Kaminski, Aya Diab
doaj +2 more sources
VIBRATION AND STRESS ANALYSIS OF A UGS ASSEMBLY FOR THE APR1400 RVI CVAP [PDF]
Nuclear Engineering and Technology, 2012 The most important component of a nuclear power plant is its nuclear reactor. Studies on the integrity of reactors have become an important part regarding the safety of a nuclear power plant. The US Nuclear Regulatory Commission Regulatory Guide (NRC RG) 1.20 presents a Comprehensive Vibration Assessment Program (CVAP) to be used to verify the ...
Do-Young Ko
exaly +2 more sources
Digitalization of the Ex-Core Neutron Flux Monitoring System for APR1400 Nuclear Power Plant
Applied Sciences (Switzerland), 2020 This work studied the feasibility of digitalizing the analog Ex-Core Neutron Flux Monitoring System (ENFMS) being used for APR1400 nuclear power plants (NPPs) and as to which strategies and steps must be taken.
Kil To Chong +2 more
exaly +3 more sources
Response Instrumentation Test Acceptance Criteria for APR1400 RVI CVAP
Transactions of the Korean Society for Noise and Vibration Engineering, 2011 ABSTRACT APR1400 RVI CVAP using the non-prototype category Ⅱ is being conducted to verify integrity of the RVI design and to secure the CVAP technology. The measurement programs are to confirm vibration analysis results for reactor internals during pre-operational and initial startup testing and to determine the safety margin.
Do-Young Ko
exaly +3 more sources
Nuclear Engineering and Technology, 2022 In the present study, the cavity module of the MELCOR code is used for the simulation of molten corium concrete interaction (MCCI) during the late phase of postulated large break loss of coolant (LB-LOCA) accident in the APR1400 reactor design. Using the
Muritala A. Amidu, Yacine Addad
doaj +1 more source
An Extended Thermosyphon Cooling System for APR-1400 Reactor Design
Case Studies in Thermal Engineering, 2021 Advanced Power Reactor (APR-1400) is a Generation III + Pressurized Water Reactor (PWRs) and has gained popularity among energy mix community. APR-1400 features enhanced safety limits to prevent a “Fukushima-type” accident scenario for a duration up to 8
Saif Y. Alhammadi +6 more
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Neutronics Assessment of Accident-Tolerant Fuel in Advanced Power Reactor 1400 (APR1400)
Atom Indonesia, 2020 Safety and reliability are the most desirable conditions that each nuclear power plant should improve. Since the Fukushima Daiichi accident, Accident-Tolerant Fuel (ATF) has been extensively researched to improve the performance of the nuclear fuel ...
D. Hartanto +5 more
doaj +1 more source
Nuclear Engineering and Technology, 2021 The analog-based Ex-core Neutron Flux Monitoring System (ENFMS) in Korean Nuclear Power Plants (NPPs) has been performing its intended functions successfully for a long time.
Young Baik Kim +2 more
doaj +1 more source