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GSW全文库(1)	CNKI会议论文(7)	CNKI期刊论文0611(2)	万方学位论文(1)
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在“Elsevier电子期刊”中，命中：796条，耗时：0.0619705 秒

在所有数据库中总计命中：1,355条

1.Using particle swarm optimization algorithm to search for a power ascension path of boiling water reactors

作者：Tzung-Yi Lin ; ^{joey.tylin@gmail.com} ; Jau-Tyne Yeh ; Weng-Sheng Kuo

关键词：Particle swarm optimization algorithm ; Power ascension of boiling water reactors ; Operating point searching strategy ; ASCENTB

刊名：Annals of Nuclear Energy

出版年：2017

2.A passive decay-heat removal system for an ABWR based on air cooling

作者：Hiroyasu Mochizuki^a ; ^{mochizki@u-fukui.ac.jp}Author Vitae ; Takahiro Yano^bAuthor Vitae

关键词：ABWR ; advanced boiling water reactor ; AC ; air cooler ; ACS ; air cooling system ; CFD ; computational fluid dynamics ; DC ; direct current ; DHRS ; decay heat removal system ; FBR ; fast breeder reactor ; HTT ; heat transfer tube ; IC ; isolation condenser ; LWR ; light water reactor ; MSIV ; main steam isolation valve ; PWR ; pressurized water reactor ; RCIC ; reactor core isolation cooling ; RHR ; residual heat remover ; SBO ; station blackout ; SCAC ; steam condensing-type air cooler ; SP ; suppression pool ; SRV ; safety r

刊名：Nuclear Engineering and Design

出版年：2017

3.Ex-vessel Steam Explosion Analysis for Pressurized Water Reactor and Boiling Water Reactor

作者：Matjaž Leskovar ; ^{matjaz.leskovar@ijs.si" class="auth_mail" title="E-mail the corresponding author} ; Mitja Ur&scaron ; ič

关键词：Boiling Water Reactor ; Fuel-Coolant Interaction ; Pressure Load ; Pressurized Water Reactor ; Reactor Cavity ; Severe Accident ; Steam Explosion

刊名：Nuclear Engineering and Technology

出版年：2016

4.Modeling heat transfer through chimney-structured porous deposit formed in pressurized water reactors

作者：D.Y. Yeo ^{ydy0131@kaist.ac.kr} ; H.C. NO ; ^{hcno@kaist.ac.kr}

关键词：Nucleate boiling ; Porous medium ; Deposit ; Wick boiling ; Steam chimney

刊名：International Journal of Heat and Mass Transfer

出版年：2017

5.A coupling model for the two-stage core calculation method with subchannel analysis for boiling water reactors

作者：Takeshi Mitsuyasu^a ; ^b ; ^{takeshi.mitsuyasu.mz@hitachi.com} ; Motoo Aoyama^a ; Akio Yamamoto^b

关键词：BWR ; Control rod ; Subchannel analysis ; Void fraction

刊名：Annals of Nuclear Energy

出版年：2017

6.Investigation of the recriticality potential during reflooding phase of Fukushima Daiichi Unit-3 accident

作者：Piotr Darnowski ; ^{piotr.darnowski@itc.pw.edu.pl" class="auth_mail" title="E-mail the corresponding author} ; Kacper Potapczyk ; Konrad Świrski

关键词：Recriticality ; Boiling water reactor ; Reflooding ; MELCOR ; SERPENT ; Fukushima Daiichi ; 1F3 ; Severe accident

刊名：Annals of Nuclear Energy

出版年：2017

7.Cofrentes nuclear power plant instability analysis using ensemble empirical mode decomposition (EEMD)

作者：C. Montalvo^a ; ^{cristina.montalvo@upm.es} ; C.J. Gavilá ; n-Moreno^b ; A. Garcí ; a-Berrocal^a

关键词：Hilbert-Huang transform ; Empirical Mode Decomposition ; Ensemble empirical mode decomposition ; Boiling water reactors ; Intrinsic Mode Function

刊名：Annals of Nuclear Energy

出版年：2017

8.Radiotoxicity implications and reduction strategies of minor actinide in a boiling water reactor

作者：Gustavo Alonso^a ; ^b ; ^{gustavo.alonso@inin.gob.mx" class="auth_mail" title="E-mail the corresponding author} ; ^{gustavoalonso3@gmail.com" class="auth_mail" title="E-mail the corresponding author} ; Eduardo Martinez^a ; ^{eduardo.martinez@inin.gob.mx" class="auth_mail" title="E-mail the corresponding author} ; J. Ramó ; n Ramí ; rez^a ; ^{ramon.ramirez@inin.gob.mx" class="auth_mail" title="E-mail the corresponding author} ; Hector Hernandez^a ; ^{hector.hernandez@inin.gob.mx" class="auth_mail" title="E-mail the corresponding author}

刊名：Annals of Nuclear Energy

出版年：2017

9.Studying the performance of dielectric barrier discharge and gliding arc plasma reactors in tomato peroxidase inactivation

作者：Mohammad Reza Khani^a ; Babak Shokri^a ; ^{b-shokri@sbu.ac.ir} ; Khosro Khajeh^b

关键词：Peroxidase ; Plasma ; Dielectric barrier discharge ; Gliding arc

刊名：Journal of Food Engineering

出版年：2017

10.ESBWR passive safety system performance under loss of coolant accidents

作者：Somboon Rassame^a ; ^{somboon.ra@chula.ac.th} ; Takashi Hibiki^b ; Mamoru Ishii^b

关键词：ESBWR ; Passive safety system ; LOCA ; Break

刊名：Progress in Nuclear Energy

出版年：2017

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