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221
Uncertainty Analysis of Method-Based Operating Event Groups Ranking
Published 2014-01-01“…An analysis was performed on the set of the two databases from the 20 years of nuclear power plants in France and Germany. From all uncertainties the presented analysis selected ranking indexes as the most relevant for consideration. …”
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222
Condition Monitoring of Sensors in a NPP Using Optimized PCA
Published 2018-01-01“…An optimized principal component analysis (PCA) framework is proposed to implement condition monitoring for sensors in a nuclear power plant (NPP) in this paper. Compared with the common PCA method in previous research, the PCA method in this paper is optimized at different modeling procedures, including data preprocessing stage, modeling parameter selection stage, and fault detection and isolation stage. …”
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223
Stress Concentration in the Bulk Cr2O3: Effects of Temperature and Point Defects
Published 2017-01-01“…Modeling the growth and failure of passive oxide films formed on stainless steels is of general interest for the use of stainless steel as structural material and of special interest in the context of life time extension of light water reactors in nuclear power plants. Using the DFT+U approach, a theoretical investigation on the resistance to failure of the chromium-rich inner oxide layer formed at the surface of chromium-containing austenitic alloys (stainless steel and nickel based alloys) has been performed. …”
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224
The Characteristics of Seismic Response on Hard Interlayer Sites
Published 2020-01-01“…Based on the engineering geological data of a nuclear power plant site, nine engineering geological profiles were created with hard interlayers of different thicknesses. …”
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225
Experimental Investigation on Out-of-Plane Flexural and Shear Performance of Half Steel-Concrete Slabs
Published 2020-01-01“…Half steel-concrete slabs have been used in nuclear power plants and high-rise buildings as floor and roof panels. …”
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226
First principle investigation of Cr doping effect on the stability of NiFe2O4
Published 2025-01-01“…NiFe2O4 is a key component of CRUD (corrosion-related undesirable deposits) that may severely degrade the safety and efficiency of nuclear power systems. Recent experimental studies showed that Cr impurity may affect the formation and growth of NiFe2O4-rich deposit on Cr-coated nuclear fuel, demonstrating a promising solution to inhibit the growth of CRUD. …”
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227
Experimental Studies of Thermal Hydraulics of Deep Eutectic Solvent Based on Choline Chloride
Published 2022-01-01“…Molten salt reactor (MSR) is considered a promising 4th generation nuclear power plant because of its safety and suitability for SMR (small modular reactor). …”
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228
Modeling of the Radiation Doses during Dismantling of RBMK-1500 Reactor Pressurized Tanks from Emergency Core Cooling System
Published 2013-01-01“…Decommissioning of the Ignalina Nuclear Power Plant involves multiple problems. One of them is personnel radiation safety during the performance of dismantling activities. …”
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229
Multi-step multivariate forecasting of transmission power in NPPs using operational and meteorological data
Published 2025-02-01“…All kinds of power plants, including nuclear power, must notify the grid operation organization of their expected transmission power. …”
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230
Analysis and Implementation of Sliding Mode Controller-Based Variable Frequency Drive Using the SCADA System
Published 2022-01-01“…To solve this problem, the proposed system combines a seven-level pulse width modulation (PWM) inverter for vector control of a three-phase asynchronous nonstandard induction machine used in critical applications in nuclear power plants with a sliding mode control technique that eliminates the complexity of PI tuning. …”
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231
‘Fission Chips’: An Activist’s View on Anti-Nuclear Activism in South Africa from the 1980s to the 21st Century
Published 2024-10-01“…Evidence of the decisive role played by Eskom is presented, while we show how energy policy became implacably skewed in favour of nuclear power by means of a ‘policy-adjusted’ IRP2010, which became the unchallenged justification for the nuclear fleet. …”
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232
Operational Characteristics of Research and Test Benches and Installations with Heavy Liquid Metal Heat Carriers
Published 2023-12-01“…Heavy liquid metal heat carriers of nuclear power plants such as lead, eutectic lead-bismuth alloy, lead-lithium, gallium alloys differ significantly in their physicochemical properties from traditional and well-studied, widely used water, sodium, as well as liquid salt heat carriers, potassium, gases (helium, etc.).…”
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233
Simulation and Analysis of Small Break LOCA for AP1000 Using RELAP5-MV and Its Comparison with NOTRUMP Code
Published 2017-01-01“…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. …”
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234
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235
Simulation of Electromagnetic Field of a Powerful Electrical Machine
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236
Interaction of Cyclic Loading (Low-Cyclic Fatigue) with Stress Corrosion Cracking (SCC) Growth Rate
Published 2020-01-01“…The structural integrity analysis of nuclear power plants (NPPs) is an essential procedure since the age of NPPs is increasing constantly while the number of new NPPs is still limited. …”
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237
The Arab world on the verge of the energy transition: Challenges, ambitions, and limits to growth
Published 2022-10-01“…The authors note that these countries actively experiment with all known renewable energy sources, including hydrogen-based, but at the same time, they are seeking to develop nuclear power. However, their ambitious projects do not reflect the real situation in the region as a whole, where most countries are extremely cautious in making risky, expensive decisions on energy and climate policy. …”
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238
A Study of the Creep-Fatigue Damage Mechanism of a P92 Welded Joint Using Nanoindentation Characterization
Published 2025-01-01“…In fossil fuel and nuclear power plants, welded joints continuously experience creep-fatigue loading, which can result in premature cracking during the in-service term. …”
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239
International Standard Problems and Small Break Loss-of-Coolant Accident (SBLOCA)
Published 2008-01-01“…Best-estimate thermal-hydraulic system codes are widely used to perform safety and licensing analyses of nuclear power plants and also used in the design of advance reactors. …”
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240
Investigation and Assessment of the CFD for Horizontal Flow in the VHTR Core
Published 2017-01-01“…A nuclear power station using gas as a cooling medium has attracted so much attention because it offers high efficiency and greater safety. …”
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