Results 21 to 30 of about 2,735 (205)

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

Microstructural and Fractographic Characterization of a Thermally Embrittled Nuclear Grade Steel: Part II - Quenching and Tempering

Materials Research, 2002
A nuclear reactor pressure vessel steel was submitted to different quenching and tempering heat treatments aimed at simulating neutron irradiation damage.
Tarpani José R., Braz Maria H.P., Bose Filho Waldek W., Spinelli Dirceu   +3 more
doaj   +3 more sources

Interpretation of Nondestructive Magnetic Measurements on Irradiated Reactor Steel Material

Applied Sciences, 2021
Neutron irradiation-generated embrittlement of nuclear pressure vessel steel was inspected by a nondestructive magnetic method, called magnetic adaptive testing (MAT).
Gábor Vértesy, Antal Gasparics, Ildikó Szenthe, Inge Uytdenhouwen   +3 more
doaj   +1 more source

Conceptual aspects of melting unit vessel cooling by heavy liquid metal coolant

Nuclear Energy and Technology, 2016
The article presents a conceptual analysis of the feasibility of lead–bismuth coolant application for cooling the melting unit steel vessel designed for implementation of a new efficient radwaste reprocessing technique.
A.Yu. Legkikh, R.Sh. Askhadullin, P.N. Martynov, V.P. Melnikov, A.N. Storozhenko   +4 more
doaj   +1 more source

Mechanical testing data from neutron irradiations of PM-HIP and conventionally manufactured nuclear structural alloys

Data in Brief, 2023
This article presents the comprehensive mechanical testing data archive from a neutron irradiation campaign of nuclear structural alloys fabricated by powder metallurgy with hot isostatic pressing (PM-HIP).
Janelle P. Wharry, Caleb D. Clement, Yangyang Zhao, Katelyn Baird, David Frazer, Jatuporn Burns, Yu Lu, Yaqiao Wu, Collin Knight, Donna P. Guillen, David W. Gandy   +10 more
doaj   +1 more source

New Dosimetric Interpretation of the DV50 Vessel-Steel Experiment Irradiated in the OSIRIS MTR Reactor Using the Monte-Carlo Code TRIPOLI-4®

EPJ Web of Conferences, 2016
An irradiation program DV50 was carried out from 2002 to 2006 in the OSIRIS material testing reactor (CEA-Saclay center) to assess the pressure vessel steel toughness curve for a fast neutron fluence (E > 1 MeV) equivalent to a French 900-MWe PWR ...
Malouch Fadhel
doaj   +1 more source

Microstructural characterisation of brittle fracture initiation sites in reactor pressure vessel steels

Nuclear Materials and Energy, 2023
Neutron embrittlement of reactor pressure vessel (RPV) steels potentially limits the safe operational time of nuclear reactors. In tested RPV steel samples microcracks are known to originate from cleaved precipitates, inclusions or grain boundaries ...
Paul Chekhonin, Aniruddh Das, Frank Bergner, Eberhard Altstadt   +3 more
doaj   +1 more source

Effect of Aging Effect on Boiling Heat Transfer Performance of Coating Surface

Yuanzineng kexue jishu
External reactor vessel cooling (ERVC) is a key technology in the severe accident mitigation strategy of third generation pressurized water reactor nuclear power plants, and the critical heat flux (CHF) determines the pressure vessel integrity.
ZHONG Dawen, LIAN Xuexin, SHI Haopeng, HAN Yucheng
doaj   +1 more source

The effects of flux on the radiation-induced embrittlement of reactor pressure vessel steels: review of current understanding and application to high fluences

Frontiers in Nuclear Engineering
It is necessary to quantify the effects of flux on reactor pressure vessel steel embrittlement under neutron irradiation, if surveillance or high-flux test reactor data is used to predict vessel embrittlement occurring at lower fluxes.
Susan Ortner, Paul Styman, Elliot Long
doaj   +1 more source

Mechanically Robust and Depolymerizable Polyesters With Near‐Complete Monomer Recovery for Circular Additive Manufacturing

Advanced Materials, EarlyView.
A sustainable δ‐lactone‐based polymer platform enables multimodal additive manufacturing through DLP, DIW, and FFF, combining tunable crystallinity, photocurable networks, mechanical robustness, and functional response. The printed materials can be mechanically reprocessed and chemically depolymerized into recoverable monomers, demonstrating a closed ...
Farzad Gholami, Rampi Ramprasad, H. Jerry Qi   +2 more
wiley   +1 more source