Results 1 to 10 of about 155 (140)

Two-Way Time-Dependent Prestress Losses of Prestressed Concrete Containment with Bonded Prestressing Strands

open access: yesBuildings, 2023
Prestressing plays a pivotal role in ensuring the tightness and integrity of prestressed concrete containment in nuclear power plants. The prestress loss reduces the compressive stress in concrete resulting from the prestressing strands and increases the
Xingyi Wu   +3 more
doaj   +4 more sources

Containment performance evaluation of prestressed concrete containment vessels with fiber reinforcement

open access: yesNuclear Engineering and Technology, 2015
Background: Fibers in concrete resist the growth of cracks and enhance the postcracking behavior of structures. The addition of fibers into a conventional reinforced concrete can improve the structural and functional performance of safety-related ...
Young-Sun Choun, Hyung-Kui Park
doaj   +4 more sources

Strain Monitoring and Numerical Simulation Analysis of Nuclear Containment Structure During Containment Tests [PDF]

open access: yesSensors
Strain monitoring during the service life of a nuclear containment structure is an effective means to evaluate whether the structure is operating safely. Due to the failure of embedded strain sensors, surface-mounted strain sensors should be installed on
Xunqiang Yin   +4 more
doaj   +2 more sources

Experimental and numerical modeling of creep in different types of concrete [PDF]

open access: yesHeliyon, 2018
Creep in concrete, play a critical role in estimating losses in prestressed concrete structures, such as bridge girders, nuclear containment vessels, etc.
D. Harinadha Reddy, Ananth Ramaswamy
doaj   +2 more sources

Nuclear Power Plant Prestressed Concrete Containment Vessel Structure Monitoring during Integrated Leakage Rate Testing Using Fiber Bragg Grating Sensors

open access: yesApplied Sciences, 2017
As the last barrier of nuclear reactor, prestressed concrete containment vessels (PCCVs) play an important role in nuclear power plants (NPPs). To test the mechanical property of PCCV during the integrated leakage rate testing (ILRT), a fiber Bragg ...
Jinke Li   +6 more
doaj   +3 more sources

Evaluation of seismic shear capacity of prestressed concrete containment vessels with fiber reinforcement

open access: yesNuclear Engineering and Technology, 2015
Background: Fibers have been used in cement mixture to improve its toughness, ductility, and tensile strength, and to enhance the cracking and deformation characteristics of concrete structural members. The addition of fibers into conventional reinforced
Young-Sun Choun, Junhee Park
doaj   +3 more sources

Effects of No Stiffness Inside Unbonded Tendon Ducts on the Behavior of Prestressed Concrete Containment Vessels

open access: yesNuclear Engineering and Technology, 2016
The numerical simulation methodologies to evaluate the structural behaviors of prestressed concrete containment vessels (PCCVs) have been substantially developed in recent decades.
Sang-Hoon Noh   +2 more
doaj   +3 more sources

Predicting leakage of the VERCORS mock-up and concrete containment buildings - a digital twin approach

open access: yesActa Polytechnica CTU Proceedings, 2022
EDF operates a nuclear power generation fleet made up of 56 reactors. This fleet contains 24 reactors designed as double-walled concrete containment building.
Laurent Charpin   +13 more
doaj   +1 more source

Pretest analysis of a prestressed concrete containment 1:3.2 scale model under thermal-pressure coupling conditions

open access: yesNuclear Engineering and Technology, 2023
In nuclear power plant (NPP) accidents, the containment is subject to high temperatures and high internal pressures, which may further trigger serious chain accidents such as core meltdown and hydrogen explosion, resulting in a significantly higher ...
Qingyu Yang, Jiachuan Yan, Feng Fan
doaj   +1 more source

Risk due to creep of prestressed concrete at moderate temperature [PDF]

open access: yesMATEC Web of Conferences, 2019
This study is a part of a French national project dealing with the mechanical behaviour of the containment vessel of French Nuclear Power Plants in case of a severe accident. The accident conditions are characterized by the increases of internal pressure,
Vidal Thierry   +4 more
doaj   +1 more source

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