Results 11 to 20 of about 72 (58)
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
doaj +2 more sources
Optimization and performance of metafoundations for seismic isolation of small modular reactors
Computer-Aided Civil and Infrastructure Engineering, Volume 38, Issue 12, Page 1558-1582, August 2023., 2023 Abstract This paper aims to study the seismic mitigation of a typical nuclear small modular reactor (SMR) where extreme loading conditions are considered by the safe shutdown earthquake. For this purpose, to reproduce the main dynamic properties of the reactor's reinforced concrete system, a detailed structural model was synthetized, also taking into ...
Tugberk Guner +2 more
wiley +1 more source
Advancing Small Modular Reactor Technology Assessment in the Czech Republic, Egypt, and Poland
Science and Technology of Nuclear Installations, Volume 2023, Issue 1, 2023., 2023 This paper introduces the utilization of the International Atomic Energy Agency’s toolkit for reactor technology assessment (RTA) application to deploy small modular reactors (SMRs) in the Czech Republic, Egypt, and Poland. The increasing demand for clean energy has led to the prominence of small modular reactors (SMRs) in addressing global energy ...
Waad Saleh +4 more
wiley +1 more source
Fault Diagnosis to Nuclear Power Plant System Based on Time‐Series Convolution Neural Network
Wireless Communications and Mobile Computing, Volume 2022, Issue 1, 2022., 2022 Nuclear power plant (NPP) is a highly complex engineering system which has typical internal feedback and strong component coupling. With these features, most NPP systems have high risk of radioactive release, which makes it essential to perform fault detection (FD) to the NPP systems.
XianLing Li +7 more
wiley +1 more source
Experimental Research for CHF Sensitivity of Heat Flux Distribution under IVR Conditions
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 In‐vessel retention (IVR) through external reactor vessel cooling (ERVC) is one of the most effective severe accident mitigation measures in the nuclear power plants. The most influential issues on the IVR strategy are in‐vessel core melt evolution, the heat fluxes imposed on the lower head, and the external cooling of reactor pressurized vessel (RPV).
Shilei Han +4 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2021, Issue 1, 2021., 2021 In response to a station blackout accident similar to the Fukushima nuclear accident, China’s Generation III nuclear power HPR1000 designed and developed a passive residual heat removal system connected to the secondary side of the steam generator. Based on the two‐phase natural circulation principle, the system is designed to bring out long‐term core ...
Feng Li +5 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020 In order to enhance the ability of severe accident mitigation for Pressurised Water Reactor (PWR), different kinds of severe accident mitigation strategies have been proposed. In‐Vessel Retention (IVR) is one of the important severe accident management means by External Reactor Vessel Cooling. Reactor cavity would be submerged to cool the molten corium
Dekui Zhan +5 more
wiley +1 more source
Science and Technology of Nuclear Installations, Volume 2020, Issue 1, 2020., 2020 Qinshan nuclear power plant is the first large Chinese‐designed nuclear power station based on pressurized water reactor, and the second generation main stream active safety injection system is adopted for Qinshan nuclear power plant. In this paper, a novel passive safety injection system (PSIS) has been proposed for ocean‐based Qinshan Phase One ...
Lin Sun +5 more
wiley +1 more source
Advances in Civil Engineering, Volume 2018, Issue 1, 2018., 2018 The purpose of this study is to investigate the soil‐structure interaction (SSI) effect on the overall risk of a PWR containment building structure with respect to two failure modes: strength and displacement. The precise quantification of the risk within the seismic probabilistic risk assessment framework depends considerably on an accurate treatment ...
Shinyoung Kwag +3 more
wiley +1 more source
Modelling of Severe Accident and In‐Vessel Melt Retention Possibilities in BWR Type Reactor
Science and Technology of Nuclear Installations, Volume 2018, Issue 1, 2018., 2018 One of the severe accident management strategies for nuclear reactors is the melted corium retention inside the reactor pressure vessel. The work presented in this article investigates the application of in‐vessel retention (IVR) severe accident management strategy in a BWR reactor.
Mindaugas Valinčius +4 more
wiley +1 more source