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在“Elsevier电子期刊”中，命中：169条，耗时：0.064969 秒

在所有数据库中总计命中：378条

1.Development of a test facility for analyzing transients in supercritical water-cooled reactors by fractional scaling analysis

作者：Thiago D. Roberto^a ; ^{thiagodbtr@gmail.com" class="auth_mail" title="E-mail the corresponding author} ; Má ; rio A. B. da Silva^b ; ^{mabs500@gmail.com" class="auth_mail" title="E-mail the corresponding author} ; Celso M.F. Lapa^a ; ^{lapa@ien.gov.br" class="auth_mail" title="E-mail the corresponding author}

关键词：Q. New reactor concepts

刊名：Nuclear Engineering and Design

出版年：2016

2.Thermo-hydraulic analysis of the supercritical water-cooled reactor core by porous media approach

作者：M.H. Rahimi ; G. Jahanfarnia ; ^{rezajahan@yahoo.com" class="auth_mail" title="E-mail the corresponding author}

关键词：Super critical water reactor ; Porous media approach ; Thermal&ndash ; hydraulic ; Core analysis

刊名：The Journal of Supercritical Fluids

出版年：2016

3.Technology Selection for Offshore Underwater Small Modular Reactors

作者：Koroush Shirvan ; ^{kshirvan@mit.edu" class="auth_mail" title="E-mail the corresponding author} ; Ronald Ballinger ; Jacopo Buongiorno ; Charles Forsberg ; Mujid Kazimi¹ ; Neil Todreas

关键词：Advanced Reactors ; Nuclear Design ; Nuclear Safety ; Offshore Power Cycle ; Small Modular Reactor

刊名：Nuclear Engineering and Technology

出版年：2016

4.Core design of a high breeding fast reactor cooled by supercritical pressure light water

作者：Takayuki Someya ; ^{russell@ruri.waseda.jp" class="auth_mail" title="E-mail the corresponding author} ; Akifumi Yamaji

刊名：Nuclear Engineering and Design

出版年：2016

5.Prediction of heat transfer to supercritical fluids by the use of Algebraic Heat Flux Models

作者：Andrea Pucciarelli^a ; ^{andrea.pucciarelli@yahoo.it" class="auth_mail" title="E-mail the corresponding author} ; Medhat Sharabi^b ; ^{Medhat.Sharabi@psi.ch" class="auth_mail" title="E-mail the corresponding author} ; Walter Ambrosini^a ; ^{walter.ambrosini@ing.unipi.it" class="auth_mail" title="E-mail the corresponding author}

关键词：AHFM ; Algebraic Heat Flux Model ; AKN ; Abe Kondoh Nagano ; RANS ; Reynolds Averaged Navier Stokes ; SCWR ; Supercritical Water-Cooled Reactor ; SGDH ; Simple Gradient Diffusion Hypothesis

刊名：Nuclear Engineering and Design

出版年：2016

6.Helical coil thermal-hydraulic model for supercritical lead cooled fast reactor steam generators

作者：Marco Caramello ; ^{marco.caramello@polito.it" class="auth_mail" title="E-mail the corresponding author} ; Cristina Bertani ; Mario De Salve ; Bruno Panella

关键词：Helical coil steam generators ; Compact steam generators ; Thermal-hydraulics ; Numerical model ; In-house code ; Liquid metals

刊名：Applied Thermal Engineering

出版年：2016

7.Supercritical water oxidation for energy production by hydrothermal flame as internal heat source. Experimental results and energetic study

作者：Pablo Cabeza ^{palabreras@gmail.com" class="auth_mail" title="E-mail the corresponding author} ; Joao Paulo Silva Queiroz¹ ; ^{joao.deq@gmail.com" class="auth_mail" title="E-mail the corresponding author} ; Manuel Criado ^{mcriado_sastre@hotmail.com" class="auth_mail" title="E-mail the corresponding author} ; Cristina Jimé ; nez ^{crisbaterna@gmail.com" class="auth_mail" title="E-mail the corresponding author} ; Maria Dolores Bermejo ; ^{mdbermejo@iq.uva.es" class="auth_mail" title="E-mail the corresponding author} ; Fidel Mato ^{fidel@iq.uva.es" class="auth_mail" title="E-mail the corresponding author} ; Maria Jose Cocero ^{mjcocero@iq.uva.es" class="auth_mail" title="E-mail the corresponding author}

关键词：Supercritical water oxidation ; Hydrothermal flames ; Renewable energy ; Reactor design

刊名：Energy

出版年：2015

8.Corrosion of engineering materials in a supercritical water cooled reactor: Characterization of oxide scales on Alloy 800H and stainless steel 316

作者：Kashif I. Choudhry^a ; ^{kchoudhry@trentu.ca" class="auth_mail" title="E-mail the corresponding author} ; Shooka Mahboubi^b ; ^{mahbos@mcmaster.ca" class="auth_mail" title="E-mail the corresponding author} ; Gianluigi A. Botton^b ; ^{gbotton@mcmaster.ca" class="auth_mail" title="E-mail the corresponding author} ; Joseph R. Kish^b ; ^{kishjr@mcmaster.ca" class="auth_mail" title="E-mail the corresponding author} ; Igor M. Svishchev^a ; ^{isvishchev@trentu.ca" class="auth_mail" title="E-mail the corresponding author}

关键词：A. Alloy 800H ; A. Stainless steel ; B. SEM ; B. XRD ; C. High-temperature corrosion

刊名：Corrosion Science

出版年：2015

9.Nuclear data sensitivity and uncertainty for the Canadian supercritical water-cooled reactor

作者：L. Blomeley ; J. Pencer ; B. Hyl ; F.P. Adams

关键词：Nuclear data ; Sensitivity ; Uncertainty ; Reactivity ; Supercritical water-cooled reactor ; SCWR

刊名：Annals of Nuclear Energy

出版年：January, 2014

10.Analysis of accidents and abnormal transients of a high breeding fast reactor cooled by supercritical-pressure light water

作者：Rui Guo ; ^{guorui@asagi.waseda.jp" class="auth_mail" title="E-mail the corresponding author} ; Akifumi Yamaji ; Yoshiaki Oka

关键词：ADS ; automatic depressurization system ; AFS ; auxiliary feedwater system ; ATWS ; anticipated transient without scram ; BOC ; beginning of the cycle ; CR ; control rod ; CSDT ; compound system doubling time ; DU ; depleted uranium ; EOC ; end of the cycle ; FPSR ; fissile plutonium serving ratio ; LOCA ; loss of coolant accident ; LPCI ; low pressure core injection system ; MCT ; maximal cladding temperature ; MOX ; uranium mixed oxides ; MSIV ; main steam isolation valve ; RCP ; reactor coolant pump ; RMWR ; reduced modera

刊名：Nuclear Engineering and Design

出版年：2015

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