Results 51 to 60 of about 176 (127)
Measurement of vibration and stress for APR-1400 reactor internals
Nuclear Engineering and Technology, 2018 The U.S. Nuclear Regulatory Commission, Regulatory Guide 1.20 needs to perform a comprehensive vibration assessment program for reactor internals during preoperational and startup testing for nuclear power plants and extended power uprate.
Do-Young Ko, Kyu-Hyung Kim
doaj +1 more source
MODAL CHARACTERISTIC ANALYSIS OF THE APR1400 NUCLEAR REACTOR INTERNALS FOR SEISMIC ANALYSIS
Nuclear Engineering and Technology, 2014 Reactor internals are sensitive to dynamic loads such as earthquakes and flow induced vibration. Thus, it is essential to identify the dynamic characteristics to evaluate the seismic integrity of the structures.
JONG-BEOM PARK +6 more
doaj +1 more source
Recent Advances in Ocean Nuclear Power Plants
Energies, 2015 In this paper, recent advances in Ocean Nuclear Power Plants (ONPPs) are reviewed, including their general arrangement, design parameters, and safety features.
Kang-Heon Lee +3 more
doaj +1 more source
OFF-SITE RADIOLOGICAL DOSE ASSESSMENT IN A SEVERE NUCLEAR ACCIDENT OF APR1400
Radiation Protection Dosimetry, 2020 Abstract Shin Kori unit 3 of Korea Hydro and Nuclear Power Co. is the pressurized water reactor of advanced power reactor 1400 (APR1400) in the Republic of Korea. A hypothetical accident was assumed for Shin Kori unit 3 to perform the time-dependent dose calculations along with the release rates of radionuclides to the environment.
Gazi Muhammad Borhan Uddin, Juyoul Kim
openaire +2 more sources
Worst‐Case Accident Analysis of Accident Tolerant Fuel in NuScale Using RELAP5/MOD3‐Based Code
International Journal of Energy Research, Volume 2024, Issue 1, 2024.Research in nuclear engineering focusses on improving the safety of light water reactors (LWRs), driven by accidents like Fukushima in 2011. The severity of this accident was a result of active cooling system failures and cladding material oxidation resulting in hydrogen explosions.
Willem Zuidersma +3 more
wiley +1 more source
Thermodynamic Evaluation Of Coupling Apr1400 With A Thermal Desalination Plant
, 2015 {"references": ["Introduction to Nuclear Desalination: A Guidebook, Technical Report\nSeries Number 400, International Atomic Energy Agency, Vienna, 2000.", "World Nuclear Association, http://www.world-nuclear.org/info/\nCountry-Profiles/Countries-T-Z/United-Arab-Emirates/ Nuclear Power\nin the United Arab Emirates, March. 2015.", "Mussie S.
M. Gomaa Abdoelatef +3 more
openaire +1 more source
Corium melt researches at VESTA test facility
Nuclear Engineering and Technology, 2017 VESTA (Verification of Ex-vessel corium STAbilization) and VESTA-S (-small) test facilities were constructed at the Korea Atomic Energy Research Institute in 2010 to perform various corium melt experiments.
Hwan Yeol Kim +4 more
doaj +1 more source
Application of a Deep Learning Technique to the Development of a Fast Accident Scenario Identifier
IEEE Access, 2020 To obtain more accurate results of probabilistic safety assessment (PSA), it is necessary to reflect more complete dynamics of nuclear power plants. In analyzing these more realistic PSA models, numerous thermal-hydraulic code runs should be performed ...
Hyeonmin Kim, Jaehyun Cho, Jinkyun Park
doaj +1 more source
DEVELOPMENT OF AN AMPHIBIOUS ROBOT FOR VISUAL INSPECTION OF APR1400 NPP IRWST STRAINER ASSEMBLY
Nuclear Engineering and Technology, 2014 An amphibious inspection robot system (hereafter AIROS) is being developed to visually inspect the in-containment refueling storage water tank (hereafter IRWST) strainer in APR1400 instead of a human diver.
YOU HYUN JANG, JONG SEOG KIM
doaj +1 more source
Nuclear Engineering and TechnologyThe U.S. Nuclear Regulatory Commission (NRC) Regulatory Guide (RG) 1.20 provides guidance on the comprehensive vibration assessment program (CVAP) to be performed on reactor internals during pre-operational and startup tests.
Jongsung Moon +3 more
doaj +1 more source