Results 41 to 50 of about 130 (115)
Effect of Air Temperature on Failure Prognosis of Passive Containment Cooling System in AP1000
Chemical Engineering Transactions, 2013 Passive Containment Cooling System is innovatively used in AP1000 reactor design in order to enhance the safety of new generation nuclear power plant.
Y. Yu, S. Wang, F. Niu
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Calculation and analysis of fast neutron fluence of pressure vessel in AP1000 reactor [PDF]
EPJ Web of ConferencesThe structural integrity of the reactor pressure vessel plays an important role in the safe operation of AP1000 nuclear power plant. Radiation damage of fast neutrons is the main factor leading to pressure vessel material deterioration.
Wang Yue +4 more
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A study on pressurizer cutting scenario for radiation dose reduction for workers using VISIPLAN
Nuclear Engineering and Technology, 2022 The operations in the design lifecycle of a nuclear power plant targeted to be decommissioned lead to neutron activation. Operations in the decommissioning process include cutting, decontamination, disposal, and processing.
Hak Yun Lee, Sun Il Kim, Jong Soon Song
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International Journal of Energy Research, Volume 2024, Issue 1, 2024.Efficient steam condensation is crucial for safe nuclear power plant (NPP) operations, preventing pressure buildup, overheating, and the release of radioactive materials. However, the presence of noncondensable gases (NCGs), such as air, nitrogen, hydrogen, or helium, can hinder the condensation process by creating a thermal resistance layer that ...
Samah A. Albdour +4 more
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International Journal of Energy Research, Volume 2024, Issue 1, 2024.After the Fukushima Daiichi nuclear accident in 2011, the performance of nuclear fuel during accidents became a matter of great concern. To address this, a new type of fuel technology called accident‐tolerant fuel (ATF) has been developed with the goal of enhancing the ability of light water reactors (LWRs) to withstand severe accident conditions. Iron‐
Khalid A. Alamri +4 more
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Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site
Science and Technology of Nuclear Installations, Volume 2024, Issue 1, 2024.The research utilized advanced PCTRAN and RASCAL software to evaluate the potential radiological impacts of hypothetical accidents, specifically loss‐of‐coolant accident (LOCA) and long‐term station blackout (LTSBO), at the El Dabaa Nuclear Power Plant. Over a span of ten years, comprehensive meteorological data were meticulously analyzed to assess the
Waad Saleh, Juyoul Kim, Doddy Kastanya
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Research Status and Development Suggestion of Numerical Reactor
Yuanzineng kexue jishu, 2022 With the rapid development of computer science and technology, numerical simulation has become one of scientific research methods after theory research and experiment research, and it is now playing a very important role in the R&D of nuclear reactors ...
WU Hongchun;LIU Zhouyu;ZHOU Xinyu;CAO Liangzhi
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Investigation of Burst Pressures in PWR Primary Pressure Boundary Components
Nuclear Engineering and Technology, 2016 In a reactor coolant system of a nuclear power plant (NPP), an overpressure protection system keeps pressure in the loop within 110% of design pressure.
Ihn Namgung, Nguyen Hoang Giang
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Science and Technology of Nuclear Installations, 2017 Many reactor safety simulation codes for nuclear power plants (NPPs) have been developed. However, it is very important to evaluate these codes by testing different accident scenarios in actual plant conditions.
Eltayeb Yousif +3 more
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WSEAS TRANSACTIONS ON ADVANCES in ENGINEERING EDUCATIONThe Passive Heat Removal system (PHRS) is designed to remove the residual heat from the core in case of a station blackout, failure of emergency core cooling system, or failure of feedwater supply through the Passive Residual Heat Removal Heat Exchanger (PRHR HX).
Mantasha Ponkty +2 more
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