Results 1 to 10 of about 111 (99)

Research on Neutronics Safety Parameters of the AP1000 Nuclear Reactor under Different Conditions

open access: yesEnergies, 2023
Changes in temperature during reactor operation may cause changes in physical parameters, leading to core overheating and accidents. It is essential to analyze and assess the safety parameters of the core under different operating conditions.
Xinyi Niu   +4 more
doaj   +4 more sources

Thermo-hydraulic Simulation of AP1000 Nuclear Reactor Fuel Assembly

open access: yesVetor, 2021
One of the challenges of future nuclear power is the development of safer and more efficient nuclear reactor designs. The AP1000 reactor based on the PWR concept of generation III + has several advantages, which can be summarized as: a modular ...
Leonardo Acosta Martínez   +3 more
doaj   +7 more sources

Definition of parameters for a test section for the analysis of natural convection and coolant loss in the AP1000 nuclear reactor by similarity laws and fractional scaling analysis

open access: yesBrazilian Journal of Radiation Sciences, 2019
The present work develops and analysis the main parameters of a test section for natural convection in case of failure of the pumping system as much as the loss of coolant in refrigeration accidents.
Luis Felipe Serra Cadiz   +3 more
doaj   +2 more sources

Radiation knowledge and anxiety levels among residents proximity to the world’s first AP1000 nuclear power unit [PDF]

open access: yesFrontiers in Public Health
ObjectiveAssess the level of radiation-related knowledge (RRK) and nuclear energy-related knowledge (NERK) among residents near the Sanmen Nuclear Power Plant, the first project adopted the Advanced Passive Pressurized Water Reactor (AP1000) technology ...
Jiadi Guo   +7 more
doaj   +2 more sources

Numerical Analysis of Turbulent Heat Transfer and Flow through Mixing Split Vane in a Sub-channel of AP1000 Nuclear Reactor

open access: yesEnergy Procedia, 2012
AbstractThis paper evaluates three-dimensional turbulent flow and convective heat transfer through mixing split vane in a single-phase and steady-state sub-channel of AP1000 nuclear reactor core by using general computational fluid dynamics code, Fluent6.3.26.Realizable K-ɛ model is used as a turbulent closure model, and the sub-channel is analyzed by ...
Wang, Shenglong   +3 more
exaly   +2 more sources

A Verticality Adjustment Technology for AP1000 Refueling Machine Mast [PDF]

open access: yesMATEC Web of Conferences, 2022
The refueling machine is used to handle the nuclear fuel assembly in the nuclear island, and is used to transport fuel between the fuel upender basket and reactor vessel core. During Unit 1 of a nuclear power plant initial fuel loading, it was found that
Zuo Changdi   +4 more
doaj   +1 more source

Deformation control during the welding of AP1000 main pump casing and steam generator

open access: yesNuclear Materials and Energy, 2021
The welding of the AP1000 Reactor Coolant Pump (RCP) casing and Steam Generator (SG) is an important issue to maintain the integrity of pressure boundary.
Guang-qing He   +6 more
doaj   +1 more source

Design and implementation of cloud platform for nuclear accident simulation

open access: yesFrontiers 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

PREDICTION OF AP1000’S NUCLEAR REACTOR PRESSURE VESSEL TEMPERATURE DURING NORMAL OPERATION

open access: yesJURNAL 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

Simulations of the AP1000-based reactor core with SERPENT computer code [PDF]

open access: yesArchive 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

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