Results 21 to 30 of about 2,771 (221)

Development and Application of AP1000 Nuclear Power Plant Equipment Reliability Database

open access: yes南方能源建设, 2022
[Introduction] The important value of equipment reliability data in nuclear power plant PSA, RCM, maintenance rules, reliability assurance program, risk guide management and other fields, puts forward the necessity of developing AP1000 equipment ...
Tianzuo QU, Qishu FANG, Yanlong QIAO
doaj   +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

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   +1 more source

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

Optimization and performance of metafoundations for seismic isolation of small modular reactors

open access: yesComputer-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

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   +5 more sources

Numerical Evaluation of Coolability Limits of External Reactor Vessel Cooling Using an Improved Thermal‐Hydraulic System Analysis Code

open access: yesInternational 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

open access: yesScience 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

Effect of MOX fuel and the ENDF/B-VIII on the AP1000 neutronic parameters calculations by using MCNP6 [PDF]

open access: yesNuclear Technology and Radiation Protection, 2019
The present work studies the effect of introducing MOX fuel on Westinghouse AP1000 neutronic parameters. The neutronic calculations were performed by using the MCNP6 code with the ENDF/B-VII.1 library and the new release of the ENDF/B-VIII ...
Reda Sonia M.   +3 more
doaj   +1 more source

Research on the sneak circuit analysis method of a thermal system based on energy flow

open access: yesEnergy Science &Engineering, Volume 10, Issue 9, Page 3358-3370, September 2022., 2022
Convert the heat accumulator to an energy flow model. Sneak circuit analysis of thermal system based on improved energy flow method. Analyze sneak paths of thermal systems with different types of heat accumulators. Abstract Based on the energy flow analysis method, this paper establishes the relationship between the heat accumulator and the thermal ...
Xiaoyu Shen   +4 more
wiley   +1 more source

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