Results 31 to 40 of about 176 (127)
Nuclear Engineering and Technology, 2023 In thiswork, a 24-month two-batch fuel management strategy for the APR1400 using LEU + has been investigated, where enrichments of 5.9 and 5.2 w/o are utilized in lieu of the conventional 4–5 w/o UO2 fuel.
Husam Khalefih +3 more
doaj +1 more source
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 The presence of a stable stratified gas cloud inside the containment near or at the flammability limit may lead to deflagration or even detonation which may challenge the containment and cause a radioactive material release into the environment. To mitigate this risk, a number of approaches have been proposed, for example, containment inerting or ...
Daegwang Hong +5 more
wiley +1 more source
Public Health Effects of Radioactive Airborne Effluents from Nuclear and Coal‐Fired Power Plant
Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021 It has been well known that nuclear power plant and coal‐fired power plant release some amount of radioactive materials during their normal operations. The purpose of this study was to compare radiation exposure doses to the public as a consequence of airborne effluents released from nuclear and coal‐fired power plants under the normal operation ...
Boldsaikhan Purevsuren +2 more
wiley +1 more source
Chromium-Coated Zirconium Cladding Neutronics Impact for APR-1400 Reactor Core
Energies, 2022 The accident-tolerant fuel concept involves replacing the conventional cladding system (zirconium) with a new material or coating that has specific thermomechanical properties. The aim of this study is to evaluate the neutronics performance of a chromium
Mohammad Alrwashdeh, Saeed A. Alameri
doaj +1 more source
FAULT-TOLERANT DESIGN FOR ADVANCED DIVERSE PROTECTION SYSTEM
Nuclear Engineering and Technology, 2013 For the improvement of APR1400 Diverse Protection System (DPS) design, the Advanced DPS (ADPS) has recently been developed to enhance the fault tolerance capability of the system. Major fault masking features of the ADPS compared with the APR1400 DPS are
YANG GYUN OH +5 more
doaj +1 more source
Evaluation of ATLHAMC12 subchannel code for total loss of flow scenario
Acta Polytechnica CTU Proceedings, 2023 The ALTHAMC12 subchannel code is a new subchannel code developed by the ALVEL company. The code is intended for DNBR safety analyses of the Czech nuclear power plants.
Tomáš Křeček, Štěpán Foral
doaj +1 more source
Assessment of Radiation Dose during the Installation and Removal of Steam Generator Primary Nozzle Dam in Overhaul Period [PDF]
Journal of Radiation Protection and ResearchBackground The installation and removal of nozzle dam work is one of the representative maintenance works in the steam generator primary side and can result in high levels of exposure due to the Chalk River unidentified deposit deposited inside the steam
Ju Young Kim +3 more
doaj +1 more source
SiC and FeCrAl as Potential Cladding Materials for APR-1400 Neutronic Analysis
Energies, 2022 The aim of this study is to investigate the potential improvement of accident-tolerant fuels in pressurized water reactors for replacing existing reference zircaloy (Zr) fuel-cladding systems.
Mohammad Alrwashdeh, Saeed A. Alameri
doaj +1 more source
Separation of Transformers for Class 1E Systems in Nuclear Power Plants
Science and Technology of Nuclear Installations, 2017 In order to supply electric power to the safety related loads, safety and reliability of onsite power have to be ensured for the safety function performance in nuclear power plants.
Sang-Hyun Lee, Choong-Koo Chang
doaj +1 more source
Major Achievements and Prospect of the ATLAS Integral Effect Tests
Science and Technology of Nuclear Installations, 2012 A large-scale thermal-hydraulic integral effect test facility, ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation), has been operated by KAERI. The reference plant of ATLAS is the APR1400 (Advanced Power Reactor, 1400 MWe).
Ki-Yong Choi +3 more
doaj +1 more source