Results 51 to 60 of about 36,185 (292)

Impingement wastage experiment with SUS 316 in a printed circuit steam generator

Nuclear Engineering and Technology
The sodium cooled fast reactor (SFR) is one of the Gen-IV reactors with the most operating experience accumulated. Although the technology level is the most mature among the Gen-IV reactors, there is still a safety problem that has not been solved, which
Siwon Seo, Bowon Hwang, Sangji Kim, Jaeyoung Lee   +3 more
doaj   +1 more source

A study on increase of vapor in PWR steam generator (Improvement of heat transfer coefficient by fin and twisted tape introduction)

Nihon Kikai Gakkai ronbunshu, 2016
Increasing the electric power of nuclear power plant is important for the economy and the environment. Pressurized water reactor (PWR) exchanges the heat of primary system with secondary system in the steam generator (SG) to generate vapor. In this study,
Kenta FUJI, Shinichi MOROOKA
doaj   +1 more source

Self‐Adhesive Conductive Elastomers for Gel‐Free Biopotential Recording

Advanced Electronic Materials, EarlyView.
σPOMaC, a self‐adhesive conductive citrate elastomer incorporating PEDOT:PSS and DBSA, enables gel‐free biopotential electrodes with stable conductivity and intrinsic skin adhesion. The composite exhibits low resistivity (∼ 0.02 Ω·cm), robust electrical performance during repeated use, and reliable on‐body ECG acquisition comparable to Ag/AgCl ...
Kirstie M. K. Queener, Alec Brewer, He Sun, Jack Twiddy, Vladimir A. Pozdin, Koji Sode, Alper Bozkurt, Michael Daniele   +7 more
wiley   +1 more source

Numerical Investigation of Fluid–Structure Interaction of Foreign Objects in Steam Generator Tube Bundles

Journal of Nuclear Engineering
As a critical component of nuclear and thermal energy conversion systems, the long-term safe operation of a steam generator depends on the structural integrity of its tube bundles.
Yuhua Hang, Heng Wang, Yuanqing Liu, Zhen Cai, Bin Zhu, Jinna Mei, Guorui Zhu   +6 more
doaj   +1 more source

ROSA/LSTF test and RELAP5 code analyses on PWR steam generator tube rupture accident with recovery actions

Nuclear Engineering and Technology, 2018
An experiment was performed for the OECD/NEA ROSA-2 Project with the large-scale test facility (LSTF), which simulated a steam generator tube rupture (SGTR) accident due to a double-ended guillotine break of one of steam generator (SG) U-tubes with ...
Takeshi Takeda
doaj   +1 more source

Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600 [PDF]

, 2006
In the present study alloy 600 was tested in simulated pressurised water reactor (PWR) primary water, at 360 °C, under an hydrogen partial pressure of 30 kPa. These testing conditions correspond to the maximum sensitivity of alloy 600 to crack initiation.
Andrieu, Eric, Cloué, Jean-Marc, Combrade, P., Foucault, M., Panter, J., Viguier, Bernard   +5 more
core   +2 more sources

Perimeter‐intensified inverse Zr‐Co oxygen carrier for biomass chemical‐looping gasification with high CO selectivity

AIChE Journal, EarlyView.
Abstract Chemical‐looping gasification (CLG) offers a promising route for renewable biomass valorization, yet conventional oxygen carrier regeneration with O₂/H₂O is energy‐intensive and often produces low‐quality syngas. Here, we develop an inverse ZrO2/Co3O4 oxygen carrier that enables selective biochar oxidation and efficient lattice‐oxygen transfer
Junling Gao, Haifeng Qi, Kun Lei, Tingwei Wang, Yijie Yang, Hongwei Li, Rongjun Zhang, Yu Wu, Canran Huang, Zhao Sun   +9 more
wiley   +1 more source

Methane Pyrolysis Performance in Catalytic Molten Media for Hydrogen Production From the Perspective of Bubble Column Reactor Design and Configuration

Asia-Pacific Journal of Chemical Engineering, EarlyView.
ABSTRACT In the hydrogen production routes from natural gas (methane), methane pyrolysis offers a cleaner option than the established steam methane reforming by producing CO2‐free hydrogen. However, in fixed bed reactors over solid catalysts, this technology experiences rapid catalyst deactivation due to carbon (coke) deposition encapsulating its ...
Muhammad Irfan Fakarudin, Luqmanulhakim Baharudin, Matthew J. Watson, Wan Nor Roslam Wan Isahak   +3 more
wiley   +1 more source

Data analysis for steam generator tubing samples [PDF]

NDT & E International, 1996
The objective of the Improved Eddy-Current ISI for Steam Generators program is to upgrade and validate eddy-current inspections, including probes, instrumentation, and data processing techniques for inservice inspection of new, used, and repaired steam generator tubes; to improve defect detection, classification and characterization as affected by ...
openaire   +3 more sources

Multi-region fuzzy logic controller with local PID controllers for U-tube steam generator in nuclear power plant

Archives of Control Sciences, 2015
In the paper, analysis of multi-region fuzzy logic controller with local PID controllers for steam generator of pressurized water reactor (PWR) working in wide range of thermal power changes is presented.
Puchalski Bartosz, Duzinkiewicz Kazimierz, Rutkowski Tomasz   +2 more
doaj   +1 more source