Results 31 to 40 of about 3,105,065 (231)

Simulation of the influence of hydrophones used for the characterization of pressure field distribution in low frequency, high power ultrasonic reactor vessels [PDF]

, 2007
This paper describes the use of a finite element (FE) modeling approach to investigate the influence of different hydrophone designs in laboratory scale reactor vessels.
O'Leary, R.L., Harvey, G., Gachagan, A.
core   +4 more sources

Effect of Neutron Fluence Rate on Irradiation Embrittlement of Low-copper RPV Steel

Yuanzineng kexue jishu
The reactor pressure vessels (RPVs) of pressurized water reactor (PWR) nuclear power plants currently in operation and under construction in China are all made of low-alloy ferritic steels obtained by quenching and tempering treatments (which meet the ...
WU Yazhen, LI Guoyun, WANG Haidong, HUANG Juan, ZHANG Haisheng, SUN Kai, LEI Yang, ZHU Lini
doaj   +1 more source

The Role of Water Chemistry for Environmentally Assisted Cracking in Low-Alloy Reactor Pressure Vessel and Piping Steels under Boiling Water Reactor Conditions

CHIMIA, 2005
The environmentally assisted initiation and propagation of cracks in structural materials is one of the most important degradation and ageing mechanisms in light water reactors (LWR) and may seriously affect plant availability and economics.
Hans-Peter Seifert, Stefan Ritter
doaj   +1 more source

Using Mini-CT Specimens for the Fracture Characterization of Ferritic Steels within the Ductile to Brittle Transition Range: A Review

Metals, 2023
The use of mini-CT specimens for the fracture characterization of structural steels is currently a topic of great interest from both scientific and technical points of view, mainly driven by the needs and requirements of the nuclear industry.
Marcos Sánchez, Sergio Cicero, Mark Kirk, Eberhard Altstadt, William Server, Masato Yamamoto   +5 more
doaj   +1 more source

A Compact Hollow Fiber Electrode Assembly Architecture for Continuous Electrochemical Marine Carbon Dioxide Removal

Advanced Energy Materials, EarlyView.
A coaxial, membrane‐integrated hollow fiber electrode assembly (HFEA) is developed for continuous marine carbon mineralization. By utilizing a sub‐millimeter inter‐electrode gap, the HFEA minimizes Ohmic losses, achieving 50% energy reduction and over 85% DIC removal.
Inhwan Park, Young Hun Lee, Jung Hun Lee, Seung‐Jeong Oh, T. Alan Hatton, Dong‐Yeun Koh   +5 more
wiley   +1 more source

Analysis of Shift in Nil-Ductility Transition Reference Temperature for RPV Steels Due to Irradiation Embrittlement Using Probability Distributions and Gamma Process

Metals
Reactor pressure vessel (RPV) steels are highly susceptible to irradiation embrittlement due to prolonged exposure to high temperature, high pressure, and intense neutron irradiation.
Kaikai Tang, Yan Li, Yuebing Li, Weiya Jin, Jiameng Liu   +4 more
doaj   +1 more source

HPC atomic simulations of defect formation and kinetic Monte Carlo simulation of material ageing [PDF]

EPJ Web of Conferences
Kinetic Monte Carlo (KMC) simulations are developed to simulate microstructure evolution under irradiation of structural materials of nuclear power plants. Methods based on rigid lattice atomic KMC and object KMC, despite some approximations, present the
Domain Christophe, Ambard Antoine, Adjanor Gilles, De Backer Andrée, Thuinet Ludovic, Becquart Charlotte S., Legris Alexandre   +6 more
doaj   +1 more source

Effects of neutron irradiation on magnetic first-order reversal curves in reactor pressure vessel steels

AIP Advances, 2020
We report results of measurements of first-order reversal curves (FORCs) for neutron irradiated reactor pressure vessel steels to seek their possible application to a nondestructive evaluation of the irradiation hardening.
Satoru Kobayashi, Hiroaki Murakami, Ákos Horváth, László Almásy, Ferenc Gillemot, Artem Feoktystov   +5 more
doaj   +1 more source

Impact of Chloride on the Environmentally-Assisted Crack Initiation Behaviour of Low-Alloy Steel under Boiling Water Reactor Conditions

Corrosion and Materials Degradation, 2022
Low-alloy reactor pressure vessel steels have a rather low susceptibility to stress corrosion cracking (SCC) in a boiling water reactor (BWR) environment if the high-temperature water contains no anionic impurities.
Stefan Ritter, Hans-Peter Seifert
doaj   +1 more source

Membrane‐aided simultaneous reaction–separation for liquid phase products

AIChE Journal, EarlyView.
Abstract Conventionally, reaction and separation are conducted as separate steps in liquid‐phase manufacturing, with products formed during reaction and subsequently separated from unreacted reagents, solvents, and byproducts. Integrating these steps into a simultaneous reaction–separation process can improve efficiency and reduce costs.
Yihan Song, Abdulmalik Dahiru, Alan Tirado, Cliff Kowall, Lei Li   +4 more
wiley   +1 more source