Results 21 to 30 of about 72 (58)
Analysis of Seismic Soil‐Structure Interaction for a Nuclear Power Plant (HTR‐10)
The response of nuclear power plants (NPPs) to seismic events is affected by soil‐structure interactions (SSI). In the present paper, a finite element (FE) model with transmitting boundaries is used to analyse the SSI effect on the response of NPP buildings subjected to vertically incident seismic excitation.
Xiaoxin Wang +6 more
wiley +1 more source
Radiation Dose Calculations for a Hypothetical Accident in Xianning Nuclear Power Plant
Atmospheric dispersion modeling and radiation dose calculations have been performed for a hypothetical AP1000 SGTR accident by HotSpot code 3.03. TEDE, the respiratory time‐integrated air concentration, and the ground deposition are calculated for various atmospheric stability classes, Pasquill stability categories A–F with site‐specific averaged ...
Bo Cao +3 more
wiley +1 more source
This paper introduces a base isolation system-tuned mass damper inerter (BIS-TMDI) hybrid system to the AP1000 nuclear power plant (NPP), which reduces seismic damage potential of the NPP structure. The effects of fluid-structure interaction (FSI) caused
Shuaijun Zhang +7 more
doaj +1 more source
On September 2021, Polish government declared that six pressurized water reactors with combined capacity of 6–9 GWe will be built by 2040 to reduce Poland’s reliance on coal. Due to the adopted schedule, construction of the first nuclear power plant will begin in 2026, with the first reactor capacity of 1–1.6 GWe to be operational in 2033.
Edyta Agata Macieja +2 more
wiley +1 more source
The passive safety systems of AP1000 are designed to operate automatically at desired set‐points. However, the unavailability or failure to operate of any of the passive safety systems will change the accident sequence and may affect reactor safety. The analysis in this study is based on some hypothetical scenarios, in which the passive safety system ...
Anwar Hussain +2 more
wiley +1 more source
Enhancing Resilience through Nuclear Emergency Preparedness at El Dabaa Site
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
Safety Enhancements for PHWRs Based on Macroscopic Losses of the Fukushima Accident
The role of nuclear energy is to supply electric power on a stable basis to meet increasing demands, reduce carbon dioxide emissions, and maintain stable electric power costs while ensuring safety. The Fukushima accident taught us many lessons for creating safer nuclear power plants.
Sang Ho Kim +4 more
wiley +1 more source
Role of Passive Safety Systems in Chinese Nuclear Power Development
Passive safety systems have been widely applied to advanced water‐cooled reactors, to enhance the safety of nuclear power plants. The ambitious program of the nuclear power development in China requires reactor concepts with high safety level. For the near‐term and medium‐term, the Chinese government decided for advanced pressurized water reactors with
X. Cheng +4 more
wiley +1 more source
Coupling of Modular High‐Temperature Gas‐Cooled Reactor with Supercritical Rankine Cycle
This paper presents investigations on the possible combination of modular high‐temperature gas‐cooled reactor (MHTGR) technology with the supercritical (SC) steam turbine technology and the prospective deployments of the MHTGR SC power plant. Energy conversion efficiency of steam turbine cycle can be improved by increasing the main steam pressure and ...
Shutang Zhu +4 more
wiley +1 more source
Study on control rod worth measurement technique under deep subcritical condition
BackgroundIn a series of startup physics tests, measuring the control rod worth is a critical means to determine whether the actual worth of the control rods matches the design values. This test ensures that the reactivity of the reactor can be precisely
SI Shengyi +6 more
doaj +1 more source

