Results 21 to 30 of about 1,504 (160)
PREDICTION OF AP1000’S NUCLEAR REACTOR PRESSURE VESSEL TEMPERATURE DURING NORMAL OPERATION
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA, 2022 Modeling of thermal-hydraulic calculations for the AP1000 core to predict the reactor pressure vessel (RPV) temperature has been carried out. The reactor’s primary coolant system transfers the heat produced in the reactor fuel during reactor operation to the steam generator.
Muhammad Darwis Isnaini +2 more
openaire +1 more source
Design and implementation of cloud platform for nuclear accident simulation
Frontiers in Energy Research, 2023 Introduction: To meet the multi-user, cross-time-and-space, cross-platform online demand of work, and professional training teaching in nuclear reactor safety analysis under the normalization of Coronavirus Disease 2019.Method: Taking the nuclear ...
Pengyu Chen +8 more
doaj +1 more source
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
International Journal of Energy Research, Volume 2023, Issue 1, 2023., 2023 The external reactor vessel cooling provides a means to stabilize the molten core inside the reactor vessel during the severe accident in nuclear power plants. For a credible evaluation of the chances of success of in‐vessel melt retention, one requires high‐fidelity predictions on the natural circulation flow around the reactor vessel and, in ...
Yeon-Gun Lee, Il Woong Park, Geng Chen
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
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 The micro‐mechanical state at the crack front is one of the key factors affecting the stress corrosion cracking (SCC) growth behavior. The mechanical heterogeneity and residual stress in the dissimilar metal welded joint (DMWJ) induce the micro‐mechanical state at the crack front to become more complex.
Shun Zhang +5 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
Innovative Design of Compact Heavy‐Load Independent Transfer Device for Nuclear Engineering System
Science and Technology of Nuclear Installations, Volume 2022, Issue 1, 2022., 2022 The transportation of heavy equipment in nuclear engineering has always been the focus of engineers, especially those transfer devices with the characteristics of small geometric size and heavy load. According to this kind of compact heavy‐load transfer device and its engineering tasks, the core problems caused by excessive vertical and horizontal ...
Hao Wan +6 more
wiley +1 more source
Simulations of the AP1000-based reactor core with SERPENT computer code [PDF]
Archive of Mechanical Engineering, 2018 The paper presents the core design, model development and results of the neutron transport simulations of the large Pressurized Water Reactor based on the AP1000 design.The SERPENT 2.1.29 Monte Carlo reactor physics computer code with ENDF/BVII and JEFF3.
Piotr Darnowski +4 more
doaj +1 more source