Results 51 to 60 of about 1,504 (160)
, 2010 A review of the status of the Areva European Prssurised Water Reactor (EPR)
Thomas, Stephen
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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
doaj +1 more source
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
wiley +1 more source
Educational Activities to Help Transferring Knowledge in Nuclear: The Seminars of Spanish Young Generation in Nuclear (Jóvenes Nucleares) [PDF]
, 2011 From its creation, Spanish Young Generation in Nuclear (Jóvenes Nucleares, JJNN), a non-profit organization that depends on the Spanish Nuclear Society (SNE), has as an important scope to help transferring the knowledge between those generations in the ...
Alvarez, A. +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
wiley +1 more source
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
wiley +1 more source
World Nuclear Industry Status Report 2013 [PDF]
, 2013 Two years after the Fukushima disaster started unfolding on 11 March 2011, its impact on the global nuclear industry has become increasingly visible. Global electricity generation from nuclear plants dropped by a historic 7 percent in 2012, adding to the
Froggatt, Antony, Schneider, Mycle
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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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Analisis Perbandingan Kinerja Perangkat Bahan Bakar Pltn Tipe Pwr Ap 1000 Dan Pwr 1000 Mwe Tipikal Dengan Menggunakan Program Komputer [PDF]
, 2014 Investigation of fuel element thermal-hydraulic characteristic is important step related to aspect of fuel bundle reactor design. This paper analyzes of the PWR AP1000 and PWR 1000 MWe Typical of fuel bundle thermal-hydraulic using RELAP5 code.
Nurmawan, A. (Arif) +2 more
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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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